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LEGAL NOTICETbls report was prepared as an accotit of Ooveroment sponsored work. Neither the United

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UC-34, PHYSICS

TID-4500

LOS ALAMOS SCIENTIFIC LABORATORYof the

University of CaliforniaLOS ALAMOS ● NEW MEXICO

The Data of Nuclear Reactor Physics,

1967-1968: A Bibliography

timpiled by

Jean Furnish

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ABOUT THIS REPORT

This official electronic version was created by scanning the best available paper or microfiche copy of the original report at a 300 dpi resolution. Original color illustrations appear as black and white images. For additional information or comments, contact: Library Without Walls Project Los Alamos National Laboratory Research Library Los Alamos, NM 87544 Phone: (505)667-4448 E-mail: [email protected]

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THE DATA OF NUCLEAR REACTOR PHYSICS, 1967-1968:A BIBLIOGMPHY

Compiled byJean Furnish

INTRODUCTION

This bibliography is a continuation of LA-3740-MS. Nuclear ScienceAbstracts for 1967 and 1968 have been searched and the pertinent abstractsarranged in the following order:

I. Critical Experiments, Reasonably Homogeneous

11. Critical Experiments, Lattices

III. Reactivity Measurements

IV. Neutron Flux Spectra

v. Neutron Cross Sections

1. Sources of data

2. ENDF/B tapes and other evaluated lists

3. Wide ranges in energy

4. Capture-to-fission ratios

5. Resonances

6. Doppler effects

VI. Laboratory Summary Reports and Miscellaneous

Within each section the abstracts are grouped first by year of appear-ance in Nuclear Science Abstracts and then alphabetically by first author(or corporate author if no individual author is given).

Critical masses of several small metal assemblies, reported in the1956-1966 search, are being reevaluated by H. C. Paxton and G. E. Hansen,who will publish results later. Changes in organization of the previoussearch are due to an expansion of neutron cross section and flux work. Ofparticular importance are the ENDF/B and other similar evaluated data files.Los Alamos sources for light isotope cross sections and the computerhandling of data files are L. S. Stewart and R. J. LaBauve, respectively.

I. CRITICAL EXPERIMENTS

Reasonably Homogeneous

196735673 (ANf-7320, PP 159~~) E~~ERIM~TAfJ A:;D THE-ORETICA L “WORK AT THE ZERO-ENERGY FAST REACTOR FRO.Andersson, T. L.: Bjoereus, L.: Hellstrand, E~;.Haeggblom, H.:London, S-O.; Tlren, L. L (Aktieholaget Atomenergf, Studsvik(Sweden)); Kockum, J. (Forsvarets Forskrdngaanstslt, Stockholm(Sweden)),

The fast reactor FRO Is a split-table machine with vertical fuelelements. A quantity of 120 kg 235Uis available aa fuel, fabricatedinto metallic plates of 20% enrichment. Of tbe first five coresstudied three (numbers 1, 2, and 4) consisted of undiluted fuel.Core No. 3 was diluted with graphite (29 v/0) md NO. 5 with VaPi2-itc (29Z) fmd polythene (7.5%). All assemblies had a thick refkto~of Cu except for No. 4, which had a U reflector. Among the ex~ri-mcnts carried out with FRO the following iteme are dealt with:critical mass, reaction ratios, central reactivity coefficients, andhetcrogcnclty effects. Measurements of reactivity,worths of multt-plylng as wrll se absorbing control rods are ,also summarized, in-cluding studies of interaction effects and streaming in empty chan-nels. Rcccntly, epcctromctry work with protcm;rccoil oounterB andDoppler mcnsurcmenta by meana of foil activation have been initi-ated. The latter have been carried out at 590”C, and preliminaryresults for 23SUand 238Uhave been obtained. The experlmeotat re-sults haye been analyzed with various models. The epectrum pro-~gram SPENG, which includes a data library, hue been used to csf -culatc core and teflcctor fine-etructure spectra mid to derivemultigroup crose-acction sets for the different assemblies. Forthe criticol-size and flux calculations the DSN end TDC transfmrttheory progrnmq hnve generally been employed and a eecond-orderpm-turbation code has been used to analyze the central reactivitymcasuretintit. -Alist of 41 references ia included. kntb)

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35667 (ANL-7320) PROCEEDINGS OF Ttip lNTEHNA-‘1’IONAL CCJNFE1lENCE ON FAST CRITICAL KXPERlhf ENTSAND THEIR ANALYSIS [HELO AT AilGONNf! N.4TIONAL LAB- ‘ORATORY, ILLINOIS], OCTOBEN 10-13, 1’366. (.4rgunnc tia-tionnl Lsb., Iii.). Contract W-31 -109 -eng-38. 8113p. (CONF-661019). DCP. CFST1.

The variou~ phases of fast reactor phyeics considered tn the con-ference were: differential and group cross ecctions, tt-sts of croaaecction scta, clcnn critical experiments rmd tbcir analyti is, cwalua-tion and compututlon techniques, Doppler end Na reuctlvity effuctn,12pcCjaI exI~crlmcnts and their nnn]yai~, spectrum M(”UbUrL.mMIt&!,experimental tcclmiquc!e and equipment, and future pru~mums. Atotal of 73 pnpers wne prurncnicd. Ai~structs were prt.lmrtni for 58of the fmptirs; 8 palwrs are iucludut under CONk’-IWl0 19; ni,=tructtifor G pupurs appcur in Nuclcnr Scicmcu Abstrntls, Vol. 21, underthe following }d~qtract ndmix!ru 19151, 17520, 194tiY, 2L’71,J, 194ti6,5GW; ono pnpcr it+ uimtracled umicr the report number Tl{t; -Rclwrt-13t14. &f. L. S.)

For abslrdcth of indit,itltd pup,,, s SCC: 344(, i, W.CI1 .- i.>.I.bJ,354!/7, J554b-3X163, 35645, and 35668 –J>,’OU.

35675 -(ANL-7320, pp 205-14) ZPR-3 ASSEMBLY 48: STUD-IES OF A DILUTE PLUTONIUM-FUELED ASSEMBLY. Broom-field, A. M.; Amund80n, P. 1.; Davey, W. G.; Gaaldlo, J. M.; IIctja,A. L.; Kenncy, W. P.; Long, J. K. (Ar~onno National Lnb., Ill.),

A series of relatively dimplo Pu-fuc]cd a~semblics with W0117degraded spectra haa been designed for study in ZPR-3. Aasom-bly 48, the flret in the series, tvas chosen as the sub]cct of an in-ternational comperiaon of fast reactor calculation techniques. Eachaeaembly in the propnsed program wU1 consist of a cylindricalcore surrounded by a depleted U blanket. fn Assembly 48 the rna-terisl constituents of the core are limited to Pu, depleted U, Na,graphite, and the stainlesa steel present in the structure and can-ning of tbe Na and Pu plates. Graphite ia included to degrade theneutron spectrum. The ratio of U to Pu in the core is 4.2. Theprogram of meaeurementa with Assembly 48 is still in progress.The rgsulta of tbe critical-masa evaluation, fission cross-sectionratio, and central perturbation measure mcnta are deacribcd, Alsoincluded is a brief ststement of the results of the neutron spectrumand Doppler coefficient measurements. A list of 11 references iaincluded. (autb)

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1967 ., -.

Critical Experiments:Reasonably Homogeneous

35b4S (ANL-73200 pp 186-93) MEA5.UREMfZNTS AND ANAL-YSISOF Al-, AI@3-, ANU MO-REFLECTED FAST CRITICAL EX#PERIhl ENTS. L3utlcr, D. K.; Doerner, R. C.; Knapp. W. G. (Ar-gnnne Natlond I ah., Ill.).

The smlcs of rrlticnl nsscmblies discussed was performed Inmmwxfinn with the promam for development of a fast W reactorfor nurlenr propulshnr. A prn~r,nrn of crltlcnl cxpcrlmcnts wasplmncd tn nhtnln some Imsic Informntirm nhout fndt M’-lmsed sys-trms. The nrrrft~ch m’lrrfmf w’ns to hcgbr with systems which hadslrendy been etutllrd, such ns AmwmMics 11 nnd 22 of ZPR:3 andA..qcmhly 1 of ZPft-6. A series of critical Conf@JIrRtiotM wasrW!NNdd In which only n single chnngc of comfxxlitlon was madefrom mm n!wcmbly to the next. The rxpcrimcnts were performedu Ith the spill -hcd anacmbl y ZPR-9. The corm were mhdc as closeapproximntlons to cylinders ns Wsstblc in the rectangular rfrawersof thr asacmhly. Criticnllty was norm,ally schie+ed by vmylng thecore radlua. fn each assembly a number of measurcmenta weremndc. In nffdltlon ty crltlcnllty, dctermlnntlons of fission-rate dls-trltsd!on, neutron Ilfetlme, and central and spatial reactivity worthvwrc made. .%me time was also spent studying properties relatedto control, tncluding thr effect of tnsertlng a rbrg of B fnto the re-flector near the core boundary. Included are: crltlcal Ity, the spa-Nal distribution o{ fiaaion rates, and the wortba of vartoua materl-nls atthe core ccntcr and rta a function of radius. (auth)

35668 - (AN b7320,- PP 57-64) lNTERCOMP~RIiOf.j OF CA L-”c(! I.fi TIONS FOR A DI LUTE PLUTONIUM- FUELEI_I FAST CRIT-ICAL ASSI;MIILY (ZPR-3 ASSEMBLY 48). Dnvey, W. & (Ar-@,nnc Nnt Iooal f.ab., Idaho Fulls,, Idaho).

An i“tcrnntionnl group of establ{shmmrts which arc actiw2 in the,flt.ld of fnst rt-mtors wns Invltcd to participate in a compmlaon oftkr- cdculatd and mcmmrcd parnmetcrs of a Pu-fue]cd, soft-sPc*’t~m. almPic-gcomctrY crlttcal ne~cmbly to be constructed fnAr~onne Natkmnl I,nborntory’s Zero Power f@actor-3 (ZPR-3).The study of this nsscrnhly, No. 48, [n the ZPR-3 serlcs, is stillfn prngross. A summary of the avnRahlc cnlculntcd dntn nnd themrasurr.mrmts nhtnbrcd is pr.esrnted. (puth) 1-------- . .

30090 (ANL-7007) PH\SICS hIEASUREMtiNT#lN TUNG-sTEN-BASED, A~MIt4UM-REFLECTED FAST REACTORS,Doerm’r, R. C.: Knapp, W. G.; Afmenas, K, K.: Karam, R. A.(Argunne N~tinnal Lab., 111.). Mar. 1967. Contrnct W-31-109-eng-38. 38P. Dep. CFSTI.

llm rcaults of measurements made on f~”r fast critical cxpcri-mrnta performed In ZPR-9 summarized In support of the rocket-deslgn rffort. The fuel is highly enriched 235U, the major rflluentla a $~’-Hc IIIIOV. nnd the rrflcctor matcrlal ts Al. Data on crono@cctlon sqtn for N’, Rc. and l“B are Included. (J. C. W.).

35663 ~ (AAEC/S-177) f3UCKLfNG AND INTEGRAL iPEC-TRUM MEASUItEMfINTS IN 2s9Pu/Be0 SUB-CRITICAL AS-SEMBLIES. Duerdcn, P. (Australian Afomlc Energy Commls-sfon Research Estatdlahrnent, Lucmi Helgbta). June 1967. 46p.Dep.

‘IIIu matcriala buckfing of four II(.cJ mudcratcd 2~Pu -Al alloyfuellcd nWtcma having L!eO-Zrnl]u utumlc ratios of 1707, 24990 .3749 und 4999 have been mcaaurud by the exponential method.

‘ Rclatlvo flealon rates of ‘sSW, 2SSUand ‘~ Pu were UIEOmeasuredin the equt,fibrium spectrum region of the uame asaemtdlea. Be-cawe of the heterogeneous nature of the atmemblles, fine s LCULMIJWcorrectlono were ●pplled, Some calculation using the CRAMdlffuslnn code umt the GYM EA code are Iocluded. (auth) -

38481 ANALYSIS (IF PuO@J~ CRITICA f. KXPKRIMENTS.wetrttnghouee Electrio CO., ~t~+rgh). ‘rane”

~;~~w~u%l. =.”, lfJ: sOG-T(JUn~1967)*From 13th AMuid Meeting of the Amurlcan Nuclctir Secltity,

~n tnepo, Calif., Jue 11-15.1967. SW CON k’-~7”cu2”

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44946 (RFP-1017) CRITICAL MA.SSES OF OIL’REFLECTED,ENRICHED trRANIUM METAL ASSEMBLIES WITH POLYURE-THANE CENTERS. Ernst, B. B. (Dow Cbem!dal Co., Oolden,CO1O. Rocky Flata Div.). Sept. 6, 1967. Contract AT(29-l)-1106. 2p. Dep. CFSTI.

The critical masses of 011 reftccted, cnrtchcd uranium apherlcalassemblies of inside uhrlum radii, 0.0, 4.017, 8.010, arrd 12.011cm with n Iow-dcnslty fnam in the central cavity were measured tobe 24.3, 31.65, 52.1, and 81.3 kg. Crltlcal maases were detcrmtnedby rcclprecnl multipllcntion measurement on fully reflected as-semblies and are compared with calculations. (auth)

469i4 ftN-1120) COMPARISON OF ORNL CLEAN CRITI- .CAL EXPERIMENTS WITH CALCULATIONS, FOX, J. K. fldahoNuclear Corp.. Idahe Frdls). Sept. 1967, ‘Contract ATflO-l)-1230. 23P. DeP. CFST1.

The accuracy nf several reactor codes has been determined fora mrlety of critictillty problems that are of Interest @ crltlcahtysafety. This waa done by comparlmms of the calcul,allons v.Ithdata on clean crillcal cxpcrimenta performed at ORNL. All ofthe systems stwficrl were moderated to some dcgrcc by hydrogen.Most of the comparisons are with data on highly enriched U fueledcores, although a few were with 2 bJ 5 ~rcent enrlch~d fuels. Afour-grnup structure wap used in all casea. Trsnspert theory wanused only for obtaining flux-weighted crOdS sectlrma. The tahulatcdrcsul(s Indicate that with properly weighted conatanta clge.nvaluecalculatimre using diffusion theery agree well with experlmenta.25 references. (auth) 1

27667 (GA-Nw Ari\’Arwiil ) rllt]iyi,k,]i,w oxm~ cmi-”C~PTS. Progress Rcpnrt for the Quarter Huflng %ptembcr 30,1964. (General I)yrrnmtcs Corp., Snn Dlcg.o, CalIf. GeneralAtomic l~iv.). f wt. 300 1964. Contract AT(04-3)-I f17. 4!lp.hr. (: FSTI.

~ffnrts during tho quarter were concentrated on npcclflc prob-lems rolo!vd to the npcclficaflona for the flrat tent module and Itssuhmqurrit Insortlnn Into EHOR. The devclepmenf nf R suitably[uelcd U@ motrlx atao contlnucrj with particular cmphaolo ~n de-

,.. . -tcrrrtlnlng the type of snmplce to he Incorporated In & next” lrra-rfiatlmr cnpsulcs. Cross section work and crltimd assembly ana-lytical calculnttnna were also done aa preliminary chccka on PWisotope cross scctlons data prlnr to Inltlatlng a conceptual dcslgnstudy of a Pu-fueled EDOR core. An examlhatlnn of some alternaiacladdl ng materlafs was urtdcrtaken. Infoqmatlon la Included corl-ccrnlng Th utllizatirm, PO utlllxallon, and EBOR test morkde de-velopment. (J. R.D.)

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196735669 (Af41. 7320, PI) fi6-78) lMPLICATI~N; 0{ RECENTF’t\ST Cl{lTlf’AL EXPItlUhtfiNTS.ON BASIC FAST REACTORI) I”SIGN l)ATA AND CA m,U fATIONAL Mf?TIIOD& Greebler,P.; Gynrry, G. 1,.; Hutchins, R. A.; SI?gal, 13. M. (General Elec-tric C[}., San .Jrrsc, CalIf.).

Recent cxpcrimrhtnl hzformntion from dllutc, Pu-fuclrd criticalasscmblkw ivns uscrt to tgst nnrl to provide ~ldnnce for improvingfast rcnctor rfcsip rkrta and calculntlonnl methods. Most of thecxprrlmrmtnl data used in this study are taken from ZPfl-111 As-scmhly 17 [the SF.FOR core mockup). The Importrmt nuclear reac- ftnr jvrr’amrtcrs were calculatwl with n numlmr of vnrlatlons in nu-clr=nr !Inta and calculntlrmaI tcrhnlqucs. An nnalysls of thecxlwrlmcntnJ and cnlculntcd results shows thnt by careful ndjust-mmt nf the lm~rtnrrt cross scctlnns, a much’ clnscr agrccmcntcan be achieved between calculations and cxperlmmrta than thathcr(,tofnrc reported. A complete cvnluatlcm was made of the cross-arctinn and resonance paramrter dnfa for Pu-239, the most lm-pnrfnnt Isotope in thle case. The new data yield good ngrcementwith the critical mass of Assembly 47. They result in a calculatedPu-239 Doppler effect thnt Is essentially zero, [n a~cement withthe measured values. A tw,o-dimtmsional carculatlon of the neutronIIft,l ime, ustng group constants that adequately account for the apa-tial variation of the neutron epcctrum, ylelda a significant improve-mcmt over that based on a one-dimensional model. A list of 40 ref-crcnccs is Irrcludcd. (auth)

8077 MEASUREMENT OF TIIE FAST- lhIPORTANCE FUNC-IJON DISTR[J3[ITION AND OF TIIE GEOMETRIC BUCKLING EM-PI, OYING A 2s2Cf SPONTANEOUS FISSION SOURCE. Greenspan,f?hud: Cady, K. B.: Aderhold, H. C. (Cornell Univ., Ithaca, N. y.),Trans. Amer. Nucl. .Snc., 9: 4?l-2(Oct. -Nov. 1966).

24183 (BNWL-SA-983) CRITICALITY OF PLUTOfiIWM COM-POUNDS IN THE UNDERMODERATED RANGE, H/Pu s 20. Han-sen, L. E.: Clayton, E. D. (Battelle-Northwest, Rlchiand, Wash.Pacifio Northwest Lab.). Oct. 27, 1966. Contract AT(45- 1)-1830.21p. DTIE.

Nuclear criticality control involves the application of criticalitydata to those operations involving flsstle materiais. A variety ofpiutonium compounds are known to exist for whioh experimental,criticality data are particularly lacking. In order ta obtain datafor nuclear safety guidance, a series of calculations were msdcto determine the bare wzd water reflected spherical criticalmaases for 12 of these cpmpounda in the undermoderated range(H : Pu s 20). Verification of the calculations was made for the’limited criticality data on homogeneous PuC+ ayatems in the ursder-mnde rated range, and comparisons also mstd~ for three heteroge-neous plutonium fueled aesembliea. (auth)

34161 CR ITICAI.”ITY OF PI.il’i ONIU>J (“fJMI’f LlJ4J)s IN T}JF~lNI)l;l?NJOJ)~I{,\~J’Jl RAN(; I . 11. [h! = 2°. l!:ln+(.n. l.. F . “lfly-Irm, F. J). (Itlt!(.llc hlr.morial Inst., Jflchlwrd, f!’~!.h.). (.”(m!tart

AT(45-1)- lK’10. fiuci. ,\ flf)i., :]: 4f11-71Aw4. 191,7).Expcrimrrrtnl criticality data do not ex~st fnr most plutonium

, compfmnrfs. To ohlain guidelines for nuclear criticality safety use,a aurvcy utilixing trmsporl-theory calculations was made 10 dc-tcrmin~ the rrit~cal masses of baro :md water-reflrwlcff spheresas a IIln{ Il(,n of (k?nslty nrrd II : Pu ratio for 12 of thcfre compnunrfsIn the undcrmrrcfcrated range (1{: Pu = 20). The compounds cm-slderod were: fMli2, PuH1, PuN, ~C, ~2C3. ~~20 ‘2°3. J’uF~.PuF,, PuCI1, w(N03)40 ~(~204)2. Alsn dcrive(i were core densityexpnncnts which permit, critical masses to bc prcdictcd for com-pnunds with ficnsitics ranging down in onc-f,iflh nf tkcir theoreticalvalues. The va]idlty nf the calculations was cxamincrJ by compar-ing rrvwltH with the limited rriticallty data on hnmfw?ncnus JlK32riystt,ms In the undcrmrrdcm!cd rangv. Comparisons were alsom:lde for PU metal sysicms and for three hctcr~jgcnc~us ~-fueled.nsscmblies. (auth)

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Critical Experiments:Reasonably Homogeneous.. . .. .

38760 c RITfcALITY OF PLUTONKJNf COMPOLJNDS IN THEUNDERMODERATED RANGE, H: Pus 20. Hansen, L. E.:Clayton, E. D, (Battelle-Pqclfic Northwest Lab., Rlchland,~aah.). Trans. Amer. Nucl. Sot., 10: 30’f-8(June 1967).

From 13th Annual Meeting of the American Nuclear Society,San Dieg~, Calif., June 11-15, 1967. See CONF-670602.

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35384 (ANL7320, pp ‘88-106) OPTIMISATION OF NEUTRONCROSS-SECTION DATA ADJUSTMENTS TO, GIVE AGREEMENTWITH EXPERIMENTAL CRITICAL SIZES. Hemment, PamelaC. E.; Pendlebury, E. D. (Atomic Weapons Research Establish-ment, Aldermaston (England)).

A method is described wblch enables adjustments of group crnsssections to bc calculated in an optimum way to fit experimentalcritlcaI sizes when resonance self-shielding is not important. Themethod uscs a lemt-squares fitting procedure and takes tnto ac-count the experimental uncertainties on the cross-section data andthe critical eizes. It la fully mechanized for uae with the IBhI-7030and has been shown to work sattsfactorlly. The machine programsfnvolved arc’briefly described and an account glvcn of some resultsobtained. The extension of the method to take into account otJrer bt-tcgral dnta, such as spectra and reaction-rate measurements, tncritical aysteme ia dlacusscd along with a way of dealtng wltb reao-nancc self-shicldtrrg. A list of 17 reference ts included. (IIuth)

ao93 hfEASUREMENTS OF k . ‘FOR A PuAI-THuRIA SU-PERCELL. Hill, N. A. (Battelle-Northwest, Richland, Waah.).Trana. Amer. NUCL Sot., 9: 447(OCL-NOV. 1966).,

38696 EXPERIMENTAL RESULTS FROM LARGE-C.4VITYREACTOR CRITICAL EXPERIMENT. Hyland, R. E. (bwtsResearch Center, Cleveland); Pincock, G. D.; Kunze, J. F.;Wood, R. E. Trans. Amer. Nucl. Sc.C.. 10: 8-9(June 1967).

From 13tfr Annual Meeting pf the American Nuclear Snciety,‘San Diego, Calif., June 11-15, 1967. See CONF-670602.. .

23606 (’M-3651) CiiITICA”L hlAhS ilF:l)UCI’lo N .f,llwIs,G~w~ A.; Mills, Carroll B. (Los Aiamos &.ientific L41, , N.Mc,x.). Dec. 1, 1966. Contract W-’J-IO5-eng-36. 14P. Ih.prnn. CFSTI $3.00 cy, $0. G5 nut.

Further study into the critical muss l,t nu..lcar lCUCtUrb IS uut -Iined. i{csults of the study are prcscnt~d (M 1. S )

10507 (ORNL-P-2741) ~HE NATfONAL CIUTICALITI’DATA CENTER. .Johnson, E. If. (Oak Ridge National Lab.,Tcnn.). [1966]. Contr~ct W-7405 -cng-26. 10P. (CON F-6612fIf+2). Dep. mn. CFSTI $3.00 cy, $0.65 mn.

Frnm Amcrlcnn Nuclcnr Soclct~, Natirmnl Topical Meeting,Nuck.ar Criticality Ssfcty, Lm Vcgmr, NCV.

A (.rltlc!alily Data Center has been cstab IIBhc,tiIt thv Oak I?idgcNatlfmal L~hor:llory under the sponsorship of the USAF(: f,w lhupurp(Jsc of c(,llt,cting from snurccs, both in the Urdtcid Stlt(”s andalm,:td. irrform~t ion applicalde to criticality safety piobl(, ms.Thejmiw lpal output f,f the Center is typified by TID-7028, “CrltlcalI)lm, uslf,ns ,,f :;y.. tf. ms~r,ntalnirr~ 73SU. Z.lnp,l, ;,,,(l z~~[].f. ~,,, { q.lf)-

71,1~.. “NIII 1(:]r S:!f,4y (hILdc .’. both of which wore originally the ‘!t . !,!1s uf Erf,!q! f.fl,nte nijl umfcr the sp(msorsh[p of the (:rntrr.“1k{. !,, rm<.r ,1,,,.llnl,.nt sumpzarizcw most of lhc rfnta svallnl,l( ntth{. Ii mc of it r put)] i[ut ion mrrt WI]] rcqu{rv frrquont oxpsn~l~m. TheI;lll,. r dncwtn+n! Is I,rrsr.ntly under rcvisl, m t<, Imnrpnrxlo fhr rrqulfs ,~f m,,!,. “r{.ft.nt mo~surcmtm!q and to rrflccf the tk~r, I,qlrn~$nt.,f 11.11.!I,IIItkcfn-cll(al analysis. I!nth rfncumrmtn nrr lt’ttcr -nnll,wllly kn.,.in nnIl u~etl (auth)

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1967

8069 CRITICAL EXPERIMENTS WITII Puf)z = llti2 FUELANII Dtf) M(NMRAIOR. Kutchrr, J. W.; I,auhy, .1. Il.: Purcell,W. 1,.; Schmld, L. C.; Wl!llamn, L. f).; Wordvn, .1. fl. Iflattelle .Northwent, Rlchlend, Wanh. ). Trans. Amer. NucI. Sec., 0:1 lh-!l(Clct. -NOV. 1966).

8065 ANALYS19 OF PLUTf)NIUM/URAMUM ALLOY-!’TWLED HEATED-GffAPtiITE EXPONENTIAL EXpERIhfENTS-1 rpockl, W, Rnstltuto de Pctrqufsns ffadlrrallva~ da [l”[vcrsl~adeolick [Ior[znntr., Rta711). T~nn. Amer. NucI. SCM..,g. 511;.17((lvt. -N(w. l!l(ifi). ,

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14068 (&NwL-347) MpLTIGROUP ANALY&IS f5F iELfiCTEDFAST CRITICAL ASSEMBLIES. Little, W. W. Jr.; Hardte, R. W.;Maas, L. L, (Battelle-Nbrthwest, Richland, Wash. Pacific North-west Lab.). Dec. 1966. Contract AT(45-1)-lb30. 29p, Dep.mn. CF$TI $3.00 cy, $0.65 mn.

A modlflcd version of the Rusatsn data compilation la used tocompute nuclear parameters for various fast critical assemblies.Calculated and experimental valuea of critical rnasa, flasionratios, and reactlvlty cocfficlenta arc compared. For the mcderata’vrrlume Pu and U aasembllea analyzed, the data predict k=ffwltblnabout 1.5%. (auth) , ‘

8063 CA~’Yi’YREACTOR CRITICAL EXPERIMENT. LoR-housc, J. H. (GeneraI Electric Co., Idaho Falls, Idaho); PlncoclqG. D.: Kunze, J. F.; Wood, R. E.; Hyland, R. ,E. T~ns. Amer.Nucl., .%C., 9: 340(Oct. -Nov. ~966)..-

40671 (AWRE-R-4/63) VERA ‘JU+ilAPHiTE REACTOREXPERIMENT. Interim Report. McTaggart, hf. H.; Goodfellow,’Ii.; Paterqon, W. J.; Wesle, J. W. (Atomic Weafmna ResenrchEstattllshment, Aidermaston (England)). [rid]. 55p. Dep.CFST1. UK.

Experimental work on a number of small faat reactor assem-blies with U-235/graphite cores and natural U reflectors is pre-sented. The object of the experiments was to provide detuiled in-formation agnhsst which the nucleat data for U-235 in the energyregion from 500 to 50 keV could be checked. Critical massea weremeasured for fiv’e asaemhlles. (auth). . ----

Critical Experiments !Reasonably Homogeneous

,46643 (oRNfA134) NEUTRON PHYSJCS DIVISION ANNUALPROGRESS REPORT FOR PERIOD ENDING MAY 31, 1967. , @uRidge National Lab., Term.), Aug. 1967. Contract W-7405-e~-26. .l$Op. Den. CFSTI.

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CRITICAIIITY STUDIES —critical mass and volume Of re -fleeted and. unrcficctrd pnrnffln-morferalcd uranium-!etra- .ffuorlde. (E)

~FWTRON5, PROh!PT —decny conw.wsts In reflected and unra.ficctcd pnraffln-mdernted uranium-tetrafluorlde as~cmblles.(E)J

URANIUM FLUORIDE UF4 —crltlcnilty studltw on reflectednnd unreftectod paraffin-moderated aemmhllea of, (K)

REACTORS, THKRMAL-crlticnl lty calculntimre ft~r, usingsllghtly enriched uranium

CRITICALITY STllDiFS—crltlcnl m~sa of pdycthylcnc-mod-cratcd and unmmicratrd cnrlchrd-uranium asncnd]llvn, (E)

URANIUM —critical m~ss of polyethylene-moderated andunmodrrntcd nssembllcs of rwtrlchrd, (E)

UiiANiUM-Z35 —critical mnas of fmlycthylmre-moderlted andunmodrrntrd asflrmblles of, (E)

CRITICAL ASSE)J lfLIKS —crltlcal rearm of polycthylcnc - .mndtsrated nnd unmoderated cnrlchcd-uranium. (i:). .-

35ti9 (ANti7320, pp 270-5) USE OF INTEG~’L MEA;SUREMENT5 AS SUPPLEMENTARY DATA IN NEUTRONCROSS-SECTION EVALUATION. Pazy, A.; Raksvy, O.: RelathY.: Yelvln, Y. (Hebrew Univ., Jerusalem (Israel)).

llrc formulation of an exact method for improvement of mlcrO-scqrlc cross-scctimr evaluation by tneans of Intcgcal experlmerrtdata is presented. Thie formulation utilizes a generaftzed leastsquares mctiod. A simple numerical example is used to Illustrate ‘t.hc m.@hod. (M.L.S.). . . . .

r

“3i693 (iNL7320, PP 550-9) THE CRITICAL EXPERI-~EtiTS AND PRELfMINAItY ANALYSIS OF MULTIFUELED,“OKUNIFORM CORE LOAfNXGS FOR THE k’AHET PROGRAM.

‘]ersladi, P. J.; Hess, A.L.;’Kucera, D. (Argonne NatiOna* Lab.,lIIL).

A series of small, Pu-plus-U-235-fueled faat re~tor cores wlfhsteed radial and axial reftectora were constmcted in Argonne’sZero Power Reactc.r-3 an part of the design program for theFARET reactor. These studies, designated ZPR-3 Assembly 46,were essentially mockups of possible lrmdinga of the FARET core.The primary obj~ctive of the stUdiea was to confirm the physicsanalyaia of multtfueled, nonuniform core loadings~ were envis-aged for the FARET system. A principal interest tn the studieswas to establish experimentally the predicted reactivity controlsfforded by the control-rod designs for FARET. The agrccmcntobtatned between calculations ond the results of experiments forcontrol-rod worth waa sufficient to ea~ablish the range of control~ssible br the FARET reactor. Of equal importance wan the tiub-atzntlatlon of the neutronic behavior of a mixed core in FARETwhen subassemblies of different types of fuels were interchanged.Analytical calculatlona werd &ne for all experiments, and themetksfs for analysla that were adop4ed are dlscusacd. fmith)

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1967

1S765 (CONF-661O19-1O) N1ti~f4~ FAST ~itillCAL ~-Pi!l{lMfiNTS IN TNE hlSCA AND 71O-CE. Petersen. G. T.;Kunze, J. F.; Wall, I. B.; Hallum, J. W.; tiwxtcrson, W. ft.; War-zck, k’. G. (Gcmcrtil Electric Co., l>lcitsuuton, Cullf. NuclearTcctmology f.kpt. ) . Oct. N)L6. Contracts AT(04-3)-lt19; AT(.tO-1)-2b47, 28P. Dep. mn. CFST1 !$3.00 cy, $0.65 mn.

From Internatlonaf Conference on Faot Crlttcxf Expe rkrrtf uaml Their Analysis, Argonne, U1.( The faat core of tbe Mixed Spectnrm Crlt@al Asucmhly (MSCA)

or the Vullecituu Atomic Laboratory, confalnrn a Ioadlng of enrlchctf~, ~tural U%, aruf lnconel. ’17w ncutrtin upcctruru In lhiu as-sembly Ie tipatlaUy atiympiutic and repruuentduvti of u dllule faatceramic reactor. MearjurcmentM rcqmrtrxi Include fis~lu!, r~tcrn of133” 21(u 2tttf, 2J4~ and t3fNp. Neutron llfe-time dctcrmllwxf hy,,pulawf m!utr’uu and l/V pulson tru!jrntitutlun, and ru~c.tlvtty worth~dctcrmtnwi by pile orncilluwr and direct pcrlud jllcu>uvcjncflU arereported, At the Idaho Teat StatIon, work in the 71O-CE c(mctin-tratcd on small, hard spectrum, refractory mcfal critical experi-ments rciatcd to space power reactor applications. Be refiecwdcores In the 20 to 50 liter range, containing essentially equal

: volume mixtures of W, fuiiy enriched U mutaf and Ta are studied.Data from the first basic critical experiment Include centralfission ratios, rdlector effects cn pnwer distribution and nc.utronlifetime, and re{ative reactivity wortis. (=uth)

35b74 (AN L-73200 ;p 195-203) R,ECENT FAST CRITICALEXPERIMENTS IN THE MSCA AND 71O-CE. Pcterecn, G. T.:Kumm, J. F.; Wall, I. B.: Hallam, J. W.; Henderson, W. B.: War-zck, F. G. (General Electrlc Co., San Jose, CalIf. NuclenrTechnology Dept.).

The fnst core of the Mixed Sprctrurn Critical Assembly containsa loading of 405 kg 23SU02, 1540, kg 23SU02, and 10I3Okg of Incohel‘In Its 400~lltcr fnst-core matrfx. Both cnlculatlon wrri cxpvlmcntrtcmm,strntr thnl Ihe neutron sprctrum {n this rrssrmhly Is spntlallyn~}mlilollr md rcprmentative Of n dllutc fast ccrnmlc rcnrtor. Re-crnl mt~:l.:!lromorrts tn be refnrtr.rf in fhls pnpcr Include fiusionrnlr~q !!f “S1l. ‘14[!. ~~511,t16U, nnrf 2s1Np, rmd ncutr,, ” lifo?lm~ RS detrrmlnrd IIv: Ivll~I.d nvutrmr nnd I/v p-riaon Ruhstlt,!tf,m, nml rcnr -tlvtty wnrthri n~ (ivtvrmtnw! hy pile oscillator, nmI ,lIr,., t pCrI,XImmrnurcments. WO* In tho 71rl-CE nt tho Mnhn lP. t Stnllfur hashem c,,ncmrtrntrd on nmnll. hnrrf-spcrtrum, rvfr nt tnry mrtnli-rltirnl ~xprrlmmtn relntcd to frpncf. fwwrr rwfrctfw nppllt.ntiwrm,In part lrulnr. R.-reflected cores in the 20- to 50-l ltrr I a“~ri c~”-taining emrm(ln]ly equal volume mixturcw of W and fully enrlchrnd

U metal arid surue Ta, hav~ been stbdied Some of Iiwue k.beni-t,il~w provi(lc nctesuury dcaigw ddta fur comi,uct epace rencttirtion hl)c utlkcca NIe prlmkl 11y dtwokd lu bltnlu IIIIyMictimeuaum, nwntsanti furulah very ust,ful mtcgral (iatu for evaiuuti.m of hilJ1c,r-encr~ cr(,ss s’xxmns and tilwcluli~cd tramqmrt prublel.ls i)ut arcpnr!wi m tills pupc,r are taken from the first busic critical cx-~rim~vil and UICIU48: tcmral fissiou ration, rcflct.ttjr L.tf(,ctrnon Itiw ..r ,Ii>triimtlon nmi ncul ron Itidime, id relntive rcuct. ivityworth=. A {Ist of l-l refcrcnc$s ia included. (auth)

d


14072 (o’& P-47’2) TEST PROGfiAM Ah PROCEDURESFOR A MOCKUP AND UFC NASA CAVITY R~ACTOR CRfTICALEXPERIMENT AT THE LOW POWER TEST FACILITY. Pin-dock, 0, D. (General Electric Co., Clnclnnatl, Ohio. NuclearMate-rklrt imd Profndnlon Operation). Dec. 23. l~c~. COn-tract AT(40- 1)-2847. 19P. Dep. mn. CFSTI $3.00 CY. $0.6Smn.

The test program nnrf prmwdures for an accurate prork-up ofa I@oeono UFt ●wcrlmcnt in thn cavity rraetor uelng atmet kf. . .

fotlowed by an snhml UFOwrpeklment ●re deeumerrted. The fuelradius in troth caaea wilt be 24 Inches or 0.67 of the cavity radius.Meacmrementa will be made to determine k excess, rod worth, re-actur material wurlha such ue fuel, At, eta., and power and fiuxdlbtrlbutlwrs In !he cavlly and rcftector regions. Tbe Purwue Ofth,. t.xperlmvntm is to di,tcrmlrw ab~olute differences bctwticn themock-up reactor utimg sOlid ahtiet fuel und the same aYat~m con-taining g+seous Uk’~. (uu~h)

4ii34 (BNwL-sA-780) TNEORETICAL AN; I,Y’SES OFmN.mGENfX)W+ PLUTONR~M CRITICAI, EXPERIMENTS.lllchey, C. R. (ffattolle-Northwef it, Rlchlmrd, Wnsh. Pacificfhrffrwc~t I,ah.). Oct. 3, 1966. Crmtraci AT(4s-1)-IR30.Icp. I}rp. C FST[.

A computnti,onnl mmlvsls rrf datn from m nccurnulntlon of clmn.rxpcrimcnts with plutonium [uclrwl nescmbllcw Is presented. Slm-plifhwtl,~n :~ppro~im~tions of the tramrport equ:ltlon and crorrnsrction rfnto are rwnluntcff. Assockdcd. errorw are predictoff.Crlticnlly ~nfe mnssc= an{! dlm(’nslmrs,arc prcsmrtcd for aquc-N. PufN03)’ srrlutlons nnd ‘3qPu-u’otcr mlxturrs. A thwry -rq,rrimrnt romparlson in presented. Calculated r=igcnvalrms nre ‘tnlwlnt,’d 39 a function of SN order nnd as n function of mrltmtrrrplcw~t!cr[ng rrrdcr. 11 rcfcrcnces. (hf. L. S.)

44947. . .

(RFP-1021) CRITICAL F.lASSES-FtjR,~ARTIALLYSTEEL REFLECTED ENRICHED URANIUM METAL ASSEM-f3LIES. Rothe, Robert E. (Dow Chemfcai Co., Golden, Colo.Rocky Flats Div.). Sept. 18, ]967. Contract AT(29-1)-11oG.16p. DeP. C FSTI. ‘

Sixty-one critical masses were mea~urcd for apher{cnl orhemispherical enriched U assemblies. The assemblies dlffercdin the rrmount of mild-steel refiector outside the U. They alsodiffered in the size of a central cavity in the [1. The cavity waejormed by the omission of small-radius U components from the ,oesembiv. This centrnl cnvlty contnlncd either air or mild steel,The criticai masses were dctcrmincd hy the extrapolation ofrrclprncal multipllcnllon data for eubcrltlcai nriscmhliea. (auth)

s5676 (ANL7320, pp 231-6) PHYSICS PAI&METERS OFLARGE DILUTE URANIUM CARBfD~ CORES. Ruacb, G. K.;~ram. R. A.: Ka@, W: Y.; Main, G. W. (Argonne National Lab.,Ill.).

Descriptions of the cores, critical masses, sodium-coefficientstudies, and radiai reactivity worthe of core materiale of largedilute uranium carbide Assemblies 42 and 5 in ZPR-6 and Aseem-biy 11 in ZPR-9 are presented. Assemblicq 4Z and 11 are zoned.core systems. Assembly, 5 is a 2GO0 liter ,carbide reactor. Thecores of all three Assemblies are similar. fM.L.S.)

8072 FAST-SPECTRUM REFRACTORY-NIETAL CffITICAL-EXPERIMENT MEASUREMENTS. Sims, F. L. (General Elec-tric Co., Idaho Falls, Idaho); Kunze, J. F.; Walsh, W, P.: Hen-derson, W. B. Trans. Amer. Nucl. Sot., 9: ,488-!l(Ort. -Nov.1!lmi).

5

1967=$ *ApD-Thf&32i) ANtiLAR”SEED-BLANKET REAC-

TOR CRITICAL EXPERIMENTS. Smith, (3. G.; Beck, J. W.:Gllcksteln. S. S.; (and others) fBettls Atom!c Power ‘Lab.. PittO-Ixsrgh, Pa.). Feb. 1967. Contract AT(ll-1)-Gen-14. 59p. Dep.mn. CFSTI $3.00 oy, $0,65 mn.

A series of one-, two-, and three-module cores cookinlng highiyenriched UOS seeds sncf ThOZ blankets have been aiudied. The pur-pose of this program watt to compare design calculations with\arious measured core parameters. These parameters includedthe critical eigcnvaiues, seed power distributions, fast and them@activation traverses, c ltfmrmal to tbermai ‘f% capture ratios,

!epiihermni to thermal ‘% fiseion ratios, thermal dlsadvantngefactors, and frtei advantage factors. In adffitlon, some information,on core Intermodule coupllng wap obtained. Each moduIe of the as-oemblles consisted of a narrow hexagonal annuiar 2SSUseed andan Inner and outer Th02 blanNet. Xfse cores were designed to be , 1nearly clean critical with no significant internal structure exceptfuel rod cladding in the active portion of the core. Thts alloweda fair test of the deeign model on highly absorbing narrow eeedregione in a ThOS blanket. The des igrs model was found io agreequite weIl with experimental resulte. The critical eigenvalues for “all coree were consistent and cJoae to unity. Near the seed-bianket.

.Interface, dlecrepancies between calculated attd experimentaliraverses were noted and havk been expialned by epectrum-welghtcd cross scctione and a higher order approximation to ,transport calculations. Monte Carlo calculation gave good agree-ment with experiment for thermai dleadvaritage factors and fastadvantage factors. Fact leakage effects were found to be ins- ,porbsnt in the calculation of the faat advantage factor in tbe acedregton. (auth) ,,.

38533 CRITICAL EXPERfMhNT9 WITH THE UOS-2 WTPERCENT PUOS BATCH CORE IN THE PRTR. ~th, R. I.;Kutcher, J. W.; Lwby, J. H. (Bnttefle- IUcifio Northwest Lab.,RfcMand, Wash.). Trana. Amer. NUCL SOO., 10: 185-6 (JLuse1967). ‘ .

From 13u3 Annual Meeting Of the ~merioen Nuolesr ~ie~sasn Die@, ~alif., June 11-15, 1967. we CON F-670 ~,02:

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io592 (LA-DC-5386) CORREtiTION5 OF EXPERIMENTSAND CALCULATIONS. Stratton, William R. (Us Aiamoa SX21-entific Lab., N. Mex.). [19661. Contract W-7405 -ent&36. 43P.(f20NF-66120&3). Dep. mn. CFSTI $3.00 cy, $0.65 mn.

From American Nuclear Society, National Topical Meeting,Nuciear Criticality Sufety, Lss Vegas, Nev.

4 theoretical technique to interpret criiical data using one-di~mmssional codca for spheres, slabs, and infioite cyihriers of ‘Stlf,2UU, and 231~ Waa ~mpared with dam determined eXpCriMenIdy.

Calculations fur highly enriched 21SUthermal and fast systems,even though cross sections fur, fast and epithersrd cores werechosen, gave satisfactory results, A tendency for progressiveoverestimates of critlcai raitii with decreasing enrichment wan .seen. A trend of (nbrcaeing wror with decreasing H#’SfJ ~tio fOrsystems enriched to S% *% or leas was noted. For a given “SUenrichment, a calcubttional bias may be determined and apphdWith ccmfid$nce. (F. S.)

Critical Experiments;Reasonably Homogeneous

“44941 (LA-3612) CfRiTtiALIT+ t)AT~ ~fiti~~~idfi,$FFECTfNG CRITICALITY OF StNGJJE HOMOGENEOUSUNITSO, Stratton, W. R. (LcM Alamos Scientific Lab., N.Mex,). July 1964.” Contract W-7405 -eng-36. 53P. DeP. ,c FS!TI.

The critical parameter of single hornogencoua unlta are exam- ,incd and tabulated. The study inclddcs botb Useor.etlcal and experi-mental results which are compared tienslvely in.order to estab-lieh the accuracy of the theoretical dscthod. The experimental dataare reduced to etandard conditions to facilitate this comparison andto invcsthgste the consiat~y of the Iargo number of cr[ticaI ex-prrimcnte. Given the validity of the calydational scheme, the,WIrioue affecte of diluente (includhg mrxferstors). reflectOre, d~-eity charges, and poiaone are studied. Finally. by application ofthe theory, reaulte are ok4ained which ate frmccessible or verydffficult- to obtain by experimental methods. (auth)

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38669 fRFP-907) ENIilCiiED URANiUM-METfi MEASURE-MENTS, NO. 1. Tuck, Grover (DOWchemical CO.O @ldenl CoIo.Rt@y Flatb Div.). Juiy 26, 1967. Contract AT(29-1)-1106. 36P,Dep. CFSTI. . .

The critical massea of oil-reflected and moderated enricheduranium (93.12%, uranium-235) spherical and hemispherical shellaseembliee have been meaaured at inside rttdii of O, 4, 6.67, 8,and 12 ccntfmetere (cm). The measurements are described andcompared to calculated values fnr spherfcal assemblies. (aptb)-. -.. . . . J.

8067 - ~IVR .CRITICALITY OF AQ~~.~~ls S~l,I~IoNs OFCENT ENRICIIED,UffANf UM. Webster, J. W ; Johnson. F R(Onk Rldgc Nntbtsni Lab., TcM.). Tram% Anwr. Nurl. See., 9614-16 (Oct. -Nov. 1966).

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‘. 38664 @pL-M-6701) CATALOOUE OF SHA ExPERI-.‘ MENTS AND CALCULATIONS. Supplement 1. Weinstein, S.;

Reiter, R, A. @olla Atomio Power Lab., Schenectady, N. Y,).““?&y 1967. Contract W-31-109 -enS_52. 16P. DeP. CFSTI”

Eight additional SHA critical configurations were aeaembledusing the first and seoond solfd homogeneous fuel materials andan asaortmeot of internal and extermi refiectora. The experi-mental vahsea of the effective multipl icatinn constant% dimen-

4 aional drawinge of the systems, and details of their constructionare presented as a supplement to the SHA catalo~e. (auth)

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22799 -(AHSB(S)Handtik-6 (pt.1)) HANDBOOK 9F EXPERf - ,NENTAL CRITICALITY DATA. PART L Chapters 1 to 4.Abbey, F. (comp.) (United K@fOm Atomic Energy AUtho#~RidcY (Enginnd]. Authority Health and S~etY ‘r~ch). o1220. Dem CFST1.’ UK..- ,.. .

Criticality dnta froni the literature aro compiled fnto tabulatedform. These tables are broken down Into: slngte unmoderaied .MU ~oree: stngle ~moderatcd plukntium cores; eingle ISSUcore-mndcratcd by dmsterlum, bcryillum, or carbon: md singfe pluio-nium cores moderated by doutcrtum, beryllibm, or carbon. Dataarc given vnrloua gcowetrlc con flmmatlono. 67 rcfccwrcce.(fJ.L.SJ

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1968

32958 (AHSf3(S)110ndbook-5 (pt,2)) hANDBOof( OF EXPERI-fsfENTAL CRITICALITY DATA. ~PART 2. CHAPTERS 5 AND 6,Abbey. F. (comp.) (United Kingdom Atomic Energy Authority,Rlsley (Englind). Authority Health and Safety Branch). 1968.124p. Dep. C FST1. UK.

Critlmllty data nre tabulntcd for: single 23SUcoros moderatedby hydrogen and single Pu cbrcs modcrnt.cd by hydrogen. ‘rhcresults for highly enriched systems are Critcgorized accordingto: unrcftccted sphcrwz of aqucoua U02FZ rtnd U02(NOj)2 andsphcricrl systems rcffcctcd with water n~d polycthylcnc; aqucouaCvllndrlral Systcnls –bo[b rcflcctcd a“d unref]~c~d; r~flected andunrcflcctc.d aquerrua parhllclcplpcd corca; uranium metal coresdllutcd with Iucltc nnd with Iucitc-graphltc; rind annular cylindricalaqucoua cores. The rcnulls for low and Intermedlrttc enrichmentSystcm8 arc rvrlcgorlr, cd as: bnro nqucoua corca IJ[ Rphcr!c=l,cylindrical, and rcctlllncar pnrallclcplpd crrnfl~uratlnna; singlematerlnl reflected syntcms; mrd comfamltc rcflcctora. Criticalitydata for hvtoro~cncous]y polso”cd aquc,ju~ ~Y8tcm8 ~re tnb”lat~,f% fueled aqucwus s,v8tc,ms arc catcgnrlzd ac~ording f.o 8pheriea1,Cyilndrlcal. or pnrallclcpiprd. 57 rcfcrcn~cs. (M.1,.s.)

35423 (APDA-224) ‘QUARTERLY T12CffNICAL PROGRESSREPORT ON A1-;C-SPONSORED ACTIVITIES, JANUARY-MARCHi968. (Atomic Power Development Associates, Inc., Detroit,Mlch.). Contract AT(ll-1)-865. 87p. Dep. CFSTI.

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CR-ITICAL ASSiSMBLIES —phy81c8 measuremcnt8 for pluto-nium-fueled ZPR-3 As8cmhly 48, analyais of one-dtmens{oml ,24-group spherical-geometry; phytrlca measure.mcnts foruranium-f uclt.d ZPR-6 Af?nembly 2, anplyals of one-dimen-$Ifmul 2 l-KroIIp spherical-x,eomctry


12087 (l\ NWIC-t72, [q, G.1-16) CIU’f’iCAl. MAsS i]if YSl(X&(Hut&-lle-Northwent, Rlr.’idamf, Wseh. Pmlflc Northwest i.,ub.).

Crltloal]ty trxperlmunta, bare and wdtw rnflect8d, weru contiw~with the 42 > 42 in, tiluh uaaembly htiVing ad)u~latjle lttlduw.. lbplutonium cone,.m rulkrn wum 51i g/lilur untf acd nwlwmc-n W.re2.3 and 5. Tlw plulwllum cuntnlncd 4.11W7‘t 7*’)Pu }Valuidhj{,,,1the t!ffcct Of VOtl!AWiWd]II, I:(ltkti I’uillfot’t l::ll~l,t, uld bud w.sllaW.IS nwfu. (:urrel:diwz s,( nlab cxIwI Il,,ental d-dot ~md Jmli d cdculat ion thuory W(,Iu in Ixx, r :,~rccnwnt. Ilu clwm ernlcal IJu uumi w:ltur rcftcctud iufllllt~j ULIL ~.i~ ~xver\m~lIt.Illy ebtlln~l~d 10bc 15.7 and 10.1 cm rcspectlv~ly fur 51Jg ~/llt~r at an acid IUOltrity of 2.3, Critlcdity expurimcnta wure perff)r~ll~ll t,) PrOvlde d.mfor nuclcur safety ~widwico on hurdling, storing, und td,l~,putgofUnited Kingdom nut typo caakm containing 6.6 kg plutomun, M,.tdeach. Exporimcnta were carrlcd out with the nine c~bku IIJIu mfrtiffc!ctcd wiih Lucitu. Flfcct of Lucitu mockrator and CJJII,IUIIIpluting wm studied qualitatively. The bare array indlc~t.d L’!w.cality at Rbout 19 caake; the reflected array g~ve luy2 c~tiks furcriticality. Crltlcal bucklings and mmscti were measured for mrange of IattIce spacings of 2.2 wt ‘~ unrlchm.f U fuel tuiwn In llsMwater. Critic:dlty experlmcnta wtire purformed in support Uftlwcm Cool~d Fwt iircuicr IluctOr (GCFiU prwram. The exij~rl.rimnta wore dusiLmzxf to sipml:tte ‘+titcr entry Into tlw GCFN tortand to check b~sic ncutronic data and computattomd techntqutia,An experimental pro ram to provide data for rfctcrmlmng thumin+tnum critical t23s ~nrichpent !,f hydrogcnuua urmzyl nitrsilu

systems waa comple(ed in tb~ PCTR. flttu reduction ml m.dymare currently in progress. Some experimental re8ult8 tire pru-8e,nted ua raw data. Tiw dud time problem conncctczf wtth Ikuwl.idpha mea urement using multi- chunnel equipment WM clruuul-

1vented by sing, essentially, n multiple single ch:mnel .qqmmk. A8y8tC122was u8acmbled employing fast 8olid state equipmcn! Intwptbut It wili be useful for cpithermai und f~t!t nuutron syblcmu. .{syatcm for esperlmcntally meanuring the pO l>ro~abiilty Of ILI~t~InOiSO fOr VWIOU5timC int12rVd S Wua asselni)lcd in bop~8 OfPImlJ.ing nrz Irukpondunt moumrtiment of the prompt neutron duc~y cl,nat:mt. A ncw acrica of criticul oxperimcnts WL8b~h~n IIIthr 1’1Illcd ?d~.98 Laboratory with Puflz-polystyrene c0mp3ct8 .mi IkuRemote Split -T~Ldu hltichino. ‘llzcsc experilt!cnts JI’C u COIIIIIVJAII*of the ixtaic rosearcb progrurn to provide dd~ for ev.liuullng ttweffcwta of moderation and 2boPu on intcrnwdi:itc ncutrun MIILX’18~plutordum flytkumfi. ‘I%u current serica nf expcrinwvd~ UIu um.ccrncd with fuel h;iving :m ntomic RIPu of 5 and a ‘40pu iwJWl~cOntont of 11.5 wt %. (auth)

21604 IfiNWL-6ff5) REAC”TOi4 PRYSICS D~PARTMENT ‘TECHNICAL ACTIVITIES QUARTERLY REPORT, CCTOf3ER,NOVEhlRF;R, DECEMBER 1967. (BatteiIC-Northwe8t. RiehlandoWash. Paclflc Northwest Lab.). Mar. 1968. contract ‘T(45-1}.1830. Imp. ~CP. cFsTf. . . .

. . .

CIUTICAL ASSEMBLfES-criUcai maas measurements in tbeCrlticrd ‘Approach Facility; neutron buckling mcasurementain the Critical Approach Facility: control rod reactivity worthmcaauremcnta in the Critical Approach Facility; neutronspectrum mcaauremcnta in bctcrogeneoua plutonium fueled, “intcpal

.

.

. . .

CRITICALITY STUf31ES-critical meaaurementa usbrg Pluto- ;trium nitrate in slab geometry

7

Critical Experiments:Reasonably Homogeneous1968

6114 ETUDIES OF CRITiCA-L ASSEMBLfESOF,HOMGGENEOU.9MIXTUREFOF PLUTONKIMOXIDE,AND POLY-Si’YRENE. Baxter, Alan M. (General Atomlo~v., @nerdDynamics Corp., San Dtego, Calif.):CIafin, E. D.; ffsnsen, L.”E.Trmts. Amer. Nucl. ti.. lO: 536 fNov. 1967). . .-------

From 15th Cooferdnce on Remote Systems Technology andAtom Fair, C~cago, rtI., Nm. &9,1967. See CONF-671102.

6119 NNMUM CRITICAL WI fiNHfcffMENT FOR URANYLNil IIATY. IIYDHIWsItN(XTS SYSTEMS, 131crman, S. R.; Hess,(i. 11. (Wnttclle- Fnciflc Northwest Lab., Rlchlnnd, Wash.).Trnns. :Amcr. NIICI. .Srw., 10: 539-40 fNov. 1967),

1.rmri 15th Crmfrrrrtcr on Remote ~stcmfj Technology andAtom Fair, chlcn~, Ill., NOV. 5-9, 1967. See CONF-6711C12., .

2114? MINIMUM C’RITICAL =6u ENRICHMENT OF HOMO-GF.tiEous, HYDROOENOuS URANYL NITRATE sysTEMs.Blerman, S. R.; Hess, G. M. (Battelle Memorial Inet., RtchlandoWash.). Nucl. SCL Eng., 3fi 135-9 (Apr. 1968). (Bf4WL-SA-1379).

The data presented critablish the mlnlmum,crltlcal enrlchmc tof ‘lSU in homogmwous uranyl nitrate at 2.104 with a standard Ydcvlalirm of 0.010 wt %. This results in a Jower limit of 2.07 wt %at the 99’}.confldcncc Icvcl. Optimum neutron moderation for 2.14,2.26, mxf 3.01 wt ‘k cnrlchcd urnnyl rdtrate homogeneous systemsoccurs nt H/U rxtlos of 8.0 ● 1.0, 9.3 + 0,5, $nd 10.5, ?espcctlvcIy,T7w mlnlmum crlthml enrichment Is the rnrtchmcnt kequlrcd toobtain an inflnltr rrcutrrm mult,tplicatlon factor of unity under con-i!ltkms of optimum moderation. (M. C. O.) “

330b2 ”””-”CRITICAL EXPERIMENTS ~Tfl H~M~&NEOUs .PU02-POLYSTYRENE AT 5 H:Pu. Bknna~, S. R.: Hfmsen,L. E.; Lloyd, N. c.: Clayton, E. D. (Broatiavcn Natlon~ Lnb.,t:pton, N. Y.). Trnrm.. Amer. Nucl. sec., 11: 380-l(June 1968).

Frnm 14th Annual Meeting of the American Nuclear Society,Toronto. See CONF-680601.

37530 (B~WL-SA-1630) CRITiCAL EXPERIMENTS WITHHc)hlOGENEQUS Pu~-POLYSTYRENE AT 5 H:Pu. Bie~mwt,S. R.; Haosen, L. E.: Lloyd, R. c.: Cla@n. E. D. (Battelle-Northweat, fil@tand, Waah. ‘ Pucific Northwest Lttb.). ” MaY 2\, ‘19L8. Contract AT(4S-1)-1830. , 13P. \CONF-680601-18).Dep. CFSTI. , .,,

. .From 14t’?rAnnual Meet;& of Ute American Nuclear .%clety,

Torontb, ?ntario.Critfcallty parem;etera for mfatures cf’fuel having an 11.5 ti %

240~ 1~~opio concentr~ion and an atomic H/Ptt ratio of 5 are

presented. Experirnentd data are obtetned from both bare and. reftectcd r,mtangular ptrslleleplpadn of m~ -polystyrene fuel.(D. C. C.) ,..

.

1-35655 COtiPARISON OF hlEASUREMfiNTS IN SNEAK-1 ANDZP14 111-41. Boehme, R.; Barleon, L,; Boehnel, K,; (and others)(Kernfrmschungszentrum, Karlaruhe, Ger.). pp 55-77 of FastReactor Phytdca. Voi. 11. Vienna, International Atomic EnergyAgency, 1968.

From Sympoalum on Fast Reactor Phyaica and Related %tfoty .Problems, Karlaruhe, Germany. See S’1’I/PUB-165(VoL2);coA’F-67i043-(vrJ1 .2).

The expcrimcntul program of the Karluruhc Faut Zeru PowerRc+tctm’ SNEAK stitrlt,d In the autumn, 19CG with mcn#urcmcnt8on a 46tJ-llt4w uranium arwmmbly, a mock-up of 21>1{ III-41. fJur-Ing a four- m{,nth IIt.rlod thrcxpcrimcmtnl ln~tullalkms und tcwh-nlf@cfl Of SN!~AK ~crc bUCCCHbfU]lyk’LIk!d, ‘~b(! lllhhl]htlil]ll~lnclu(Jc n nmvuhiu druwcr cunnt.f.hd [U un nuti~mntlc ~unlplechanger upt:raling III n hwizontul expcrlmcntnl chuntIi.1, a w2rtl-cal drive unit, a PIIv oscillator, and a puhwd nc.ut run ~cncrnt or.Tlm tcchniqueb umtd include spectra mcasurcmcnt~ with protonrecoil cuuntura and fuil activation, and acvcml tcchnIquca fordctcrmirdng rcac’tf~r power and /1/1, e.g., I{uMbi- und puised ncu-.-. , ,.

tron 6ource meaaurementso In the experimental program quantl -tiea such aa critical maas, react(on rate ratio a, neutron aptctrum,material wortbe in the center, radtal and axial traverses, 13/L, aodreactor power were determined The result~ were generally ingood egrccment wtth those of the ZPR 111experime-.ts, and theremainbrg diacrcfxrncicw are dlacusa~d. These are partly due tosmall deviatlona In tbo material com~sltiun of the two a6tmm-bllea. The experimental data are also compared with cdculationausing the 16-group YOM, 26-group KFK, and 26-group AfJS croha -section acts. Whiie critical maae ia best calculated with YOM, the

● YOM spectmm ia too hard, and both KFK and AltN give betteragreement wtth tbeexperimental spectrum. (auth]

‘2S078 (CEA-R4367) EXPERIENCES DE-CRITICITE REALI-SERS AVEC UNE SOLIITION HOR1OGENE DE PLUTONIIW. RE -S~lLTATS EXPfjR[hIENTAU)(. INTERPRETATIONS THEOfUQUES,(CrItkal ExwrIments Cxrried Out with a Homogwwwua PlutoniumSolution. Experimcntnl Hesulta. Theoretical Interpretations).Bouiy. Jean Claude; Caizergues, Robert; f)ellgnt, Edouard; Houelle,Mlchel; Lecorche, Pierre (Cornmlssnriat a l’Energie Atomique,Saclny (France). Centre d’Etudes Nucleaires). Dec. 1967. 90P.ffrr French). Dep.

Resuits of a series of cxpcrlmental ,nnd thcoret[cal crltlcxlttystudies on piutonlum nrt. glvcn. A comparison of thcoroticai andexpdmcntef vaiues for crlticnl hetghta of solutions is made; cf-fecta of nltrogcn, Introduced in the form of the nitrate Ion, on thereactivity of the flqsile media ●re evaiuated; the effccta of ‘topuon the reactivity of the media are analyzed. fnfluence of moder-ator which arc Introducwl [nto the aolutloo 18 tnvestigatcd; “ef-fects of dfmcneions of the Inner cavity of annular cylbrdera arermxiyzed. (nuth) ..

48735 (NP-17606) CRITICALITY OF THE LIQUID MIX-TURES OF HIGHLY-ENRICHED UFO AND HF. Caizergue.%Robert; Deilgat, Edouard Leeorche, Pterre; Maubert, L~SIRevel, Henri (Commfaearlat a l’Energte Atomtque, Saclay(France). Centra d’Etudes Nucjesfrea). Apr. 1968. 68P. (InFrench). (R-68.1). Pep.

Critical m-as la determined for ● UFC-NF mlxturc aa a functionof ‘%J concentratloru thv Uquld-vapot’ cqutlibrium IS establlahcdfor the system. Schcmattcs of the UF,-HF circuit are shou n,experimental app..ratue in dcacribed. Dcnx{ty of the hlnsry systemia tabulated aa ● function of temperature; critical urrnnlum ron-centrntlon la shown an a function of temperature. Varlatlon ofthe cffcctlve multlpllcatlon coefficient in shown an a functionof sphere dlnmctcr. Effects of the wall of the sphere and tem-perature effects on the reactivity 0[ the mlxtu.re are rfetermlned.

,~ referencca. (M. L. S.)

.

.

8

1968 ---47022 MULTIREGION FAST REACTOR EXPERIMENTS. ‘Cnrpcnter, S. G.: Mountford, L. A.; Springer, T. H.; fltromhgeriD.; Tuttle, R. J. pp91-1090f I Reattorl Veloci. Rome, ComltatuNazInmtle Energia Nuclenre, 1967.

From 6th Nuclear Congress, Rome, June 1963. See CONF-193-(VO1.2).

Adencrlptton tian Al-23 SU-fuelti crlHcal asaemblylspre-rwnted. The critical aescmbly usea reduced-denalty Al for Na and”.grnph{tcamt De for moderators. CaIculationa for the klneticpr,op- Iertlcsof theninecrltlcal aaaembliea arepreaenti. (auth)

60760 DETERMINATTONOF EFFECTS OF CRO~SEC-TION KRfIORS ON FAST REACTOR CALCULATIONS. Celentano,Romano; Gandbd, Augusto (CNEN, Rome). PP 71-85 of Fisicadel Renttore, Rome, Conrtlgllo Nazionale delha Rlcerche, 1966.(In IIallan). ‘

1,F rom Conference on Physlca of Reactors, Milan. See CON F-469.

Fuel volume fractions for six reference fast reaMQr cores aretabulated; core volumes rang? from 400-2590 L Semaltlvlty ofreactivity to change tn, cross scctlon is evaluated; Feaulta are tabu-Iatcrl for each core volume. Effects of cross section varlatlon oninitial converslbn factora 18 dlscusaed. (M. L. S.)

36637 INVESTIGATION OF THE CRfTICALiTY OF LOW-EN IUCHMENT URANIUM CYLINDERS. Chezem, C. G. (LosAlamoa Scientific Lab., N. Mex.). Nucl. Sci, I@., 33: 139(1968).

An attempt to achk-ve a near-critical asaombly with a minimumaverngc 2~’Uenrichment of an unroflectcrf, uranium metal, 21-in .-diam cylinder has beeq completed. Data wr2re required for thedesign of a low-enrichment, uranium metal, reflected system.Utilizing only the materials on hand, 21-in. -dlamoter plates of93.3% enriched uranium and normai uranium, four” low-enrichmentcylinders were investigated. The thickness of the normaI uraniumplntcs dictutcd the exact enrichments attainable by tntcrleav’Mg theplates in a cyclic manner along the axie. The critical frarameterowere obtained by extrapolation of inverse multiplication curves, ‘which extend to 93 to 95%,of the critical height. Corrections for ‘the reflecting properties of the vertical support structure and thebuilding itself were applied. The significant results are tabulated.A }east-squareg analysis (quadratic) of the data, inverse criticalheight equarcd va percent enrichment, yields results which ex-trapolate to an inffnite-height enrichment of lb.5 ● 0.2%. (auth)

3896 [R FP–1033) ‘ CRITfCAL”hlASSES “OF STEEL-MOD- .ER.ATED, ENRICHED URANIUhl hlETAL ASSEMBLIES WITHCOMPOSITE sTEEMIL Rfi FLECTCJHS. Cootileld, Donaid C.;Tuck, Grover; Clark, Haroid E.; Ernst, Bruce B. (f)uw Chem’i-cai Co., Golden, Cuio. Rocky Flats iJiv. ). Nov. ‘7, 196’7. Con-tract ATI29-1I-1106. l~p. fJep. c i“sT1.

Critic;tl m:wscs h~ve k,en dctc,rmincd, esperimenttdly and cai-wiated, fur w~rtchcd U metzi spheriml assemblies, moderated in-ternally with u sphere of mild steel of radius 8.01 centimeters.The assemblies were rctlwtcd with w+rioua thicknesses of mildsteei fulluweti by tin effectively infinite iimount of oil. An irregu-larity was noted in the graph of the expt?rimcntal and cslculalc!dcriticai masses :IMu functicm of reflector steel thickness. t~uth).

33035 A “BENCHMARK” SERfES OF PLUT’ONfUM-FUELEDFAST CRITICAL ASSEMBLIES.’ Davey, W. G. (ArgO~o NatiOn~,Lab., Idaho Falls, IdaM); Broomfield, A. M.; Amundeon, P. L;(and others). Trans. Amer. Nucl. SM., 11: 239-40 (June 1966).

From 14th Annual hfeeting of the American Nuclear Society,Toronto. See ~ONF-ti80601.


33123 : KRfTICHEb~lYE PA RAMETRY SISTEM S DE LYASH -CHIMISYA VESHCHESTVAMI I YADERNAYA BEZOPAS140STC;SPfLAVOCHNfK, (Critical Parameters of Systems With Fission-able Materials and Nqciear Ssfetfi a Handbook). Dubovakii, B. G.:Kamaev, A. V.; Kuzneteev. F. M.; (and others). Mosmw, Atrnn2z-dat, 1966. 225p.

Presented la a handbook intended for spcclaIiats concerned wltbthe problems of as~urlng nucJear safety, for persons calculating, :dcsi~lng, operating, and etudying the physics of nuclear reactoroof varioua typ&, and for studente fn associated depsrtmcnta.M@mda of creating nnd maintaining conditions which will excludethe possibility of an accidental chain reaction during the pro-cessing, storage, and trmraportation of fissionable matcriala are. . .—. . . . . .ctlscussed. mm book ia based mainly on the rcaui~ of atudlespubiiahcd before 1965. In addition to lnformdtion on critical pa-rameters of aystcma wtth fteslonable mnteriflls, the fundnmonfalconccpta of criticality, princlplm for assurln~ nuclcor ‘nnfctv. arcvlcw of cnaca of the occurrmwc of unmmlrnllrd chnln rcnrtiona, ‘and the bnaic stsndarrts for nuclcnr safety nre Included. (ATfU

32975 (LA-3&83) CRfTICAL DIMENSIONS OF” HOMOGE- ‘NEOUS SPHERES CONTAfMNG ‘%, 2J8U, AND CARBON FORVARIOUS C/ 23SURATIOS AND 23SUENRICHMENTS. Engle,L. B.: Stratton, W. R. (Los Alamos Scientific Lab., N, Mcx.).Dec. 15, 1967. Contract W-7405 -eng-36. i 3P. Dep. C fWTI.

The crltlcnl dlmens!ons of homogrnc’bus spheres containing 2%J,2~u ~d carh~n at various C/2uU moderating ratios and 23% en-richments are presehted. Some values of k- for these mixturesare included. (auth)

‘2324 (RFP-1025) CRfTiCAL MA*ES OF SPHERICAL ‘ANiJ Hf?MiSPHERfCAL STEEL-MODERATED, OIL-REFLECTEDENRICHfW URANIUM ASSEMBLifXi. Ernst, Bruce n.; nckGrovek IfJow Cbemicaf Co., Golden, Colo. Rocky k’lata Div.).NOV. 6, 1967. Contract AT(29-1)-1106. 8p. Dep. CFSTI.

Criticai masaea were experimentally determined for steel-moderated, oii-reflected, sphcricai and hemispherical enricheduranium assemblies having inside radii from 0.0 to 12.0 cm.(auth)

18573 EXperimentS ON THE ZR-9 CRITICAL MiSiMBLYIN CONNECTION WfTH THE DEVELOPMENT OF THE WWR-SMCORE. Frankl, Laazlo; Gacai, Lajoa: Szabo, Ferenc; .%aklajda,Laezicx Vsrkonyi, Lajos. KFKI (KOZP. Fiz. Kut. Intez.) Koziem,,16i 3-33(1968). ffn Hungarian).‘ The ZR-3 critical system was built as a Part Of me inte~atiohal

cooperation for the rec0n6tructi0n of the M-S ‘react0r8. Theoptimum configura~ion ‘of the WWR -FIMreactor and a possible 10S6fo~ t~e second ope ration+l cycle were evaluated on thfs zero powercritical assembly. The resulte of measurernenta carrfed out onthese two core configuration arc given. (suth)

33059 nmwfftmxmm OF” THE CRITICAL MAS9 OF AWATER-REFLECTED PLUTONIUM SPHERE. Geer, W. U.iSmith, David R. (Lea Ahunos Scientific Lab., N. MeX.). Trans.Amer. Nucl. Sot., 11: 378(June 1968).,

From, 14th Amual &teeting of tbe American Nuclear .!?ociety,Toronto. See CONF-S80601,

9

1968%417 (LA-DC-9370) MEASUREMENT OF THE CRITICAL

h!A.SS OF A WATER-REFLECTED PLUTONIUM SPHERE. Geer,W. U.: Smith, Davfd R. (Los A@mos scientific Lab., N, Mex.),.[rid]. Contract W-7405 -eng-36. 3p. (CONF-660601-39). Dep.CFSTI.

From 14th AnnuIIl Meeting of the American Nuclear Booiety,Toronto, Ontnrlo.

Crltlcafity mcasuremenfd for a water-reflected Pu ophere arepreeented. The high rmrity plutonium wae fabricated and ma-chined inio a mass of 5546 g. The ephere wae coated with Co and ‘encl oecd in a Piexlgiess shcli. Monitoring of the neutron countingrate due io the Pu provided frequent checks of the multiplicaficmof the sphere as water wae elowly added io tho epherc-contnfniqf4 x 4 ft tank. fhe-dimensional DTF cafculatione are prcsontcd.The s~ere wae remacftfned to remove 200 g md the water-addingprocedure repeated. Results are dfscueeed. (D.C.C.)

. .

18S47 (f.IOCK~T-50231-1) SOUTHWEST EXPERIMENTALFAST OXIDE REACTOR. Faciilty Description and Sefety Ansiy-❑is Report, Amendment 6, Suppl. 1. (General Electrfo CO.,Sunnyvale. Caflf. Advanced Prmfucte operation). Dec. 7, 1967.57p. DefI. CFSTI.

Supplementary information on anaiyeie of SE FOR mockup ~riticalexperiments in Z PR-3 in given. in fornmtion inclttdeo: ratio ofprompt neutron lifett me to effective delayed neutron fraction a, ,reaction ratiom reaction-ntte trsvereea, 23@u trsvereee, and soevaIuatiOn of reflector leakage probsbilitlee. 24 references. “(M, I.. S.)

30303 (GEAP-5271) IMPLICATIONS OF RECENT FASTCRITICAL ExxmmmnrrsON BASIC FA5T REACTOR DESIGNDATA AND CA LCULATIONAL METHODS. Greebier, P,; Gyorey,G. L.: Hutchfngs, B. A.: Segpl, B. M. (General Ele&ric Co.,Sunnyvale, CalIf. Advanced Products Operation). Oct. .1967. .Contract AT(04-3)-169. 37p. Dep. CFSTI.

Recent experimental information from diiute, Pu-fueled crlticeiaeaemblies ie used to teet end to provide guidance for lmtirovi9gfast reactor design data and calculational methods. The ex eri-

8menkd dttte are taken from ZPR-111 Assembly 47 (the SEF R coremockup) and ZPR- ff.f Assembly 48. The important nuciear reactorparameter are calculated with a number of vaqiat(one in riucleardata nnd calculattonrd techniques. An enaiysis of the experimentaland calculated results ahowe that by, carefui adjustment of ibe im-portant cross secUonS, WC1lwithin experimental uncertainties, sndby improved accuracy in the caiculational rnctbods, a much cloeeragreement can be achieved between calchdatfons endexperiments

. \han that heretofore reported. A complete evacuation ie made of(hc croes-acction and resonance parameter data for Pu-239, themdst i~portant isntope in this case. The new data yield good agree-ment with the’ critical mnssed of ZPR-111 Assemblie,e 47 and 48. ,They result in a calculated 23SPUDoppler effect that ie essentiallyzero, in agreement with the meaaured valuee. “A twq-dimene ionalcalculation of the neutron lifetime, using ‘group constants that sdeqdatcly ~ccount for the spatial vsrtation of the neutroh spectrum.y[clds a significant Improvement over’ that bas-kd on a one-dimcneionai modei. (50 references are included). (auth) ,

Critical Experiments:Reasonable Homo~eneous

;s089 ‘(LA-DC+521) MINIMUM CRITICAL MASS. Jarvls,George A.; Mine, Carroli B. (f.me Alsmoe Scientific Lab., N.Mex.). [rid]. Contract W-740 S-eng-36. 10p. Dep. CFSTI.

A cubicai core of enriched (93.15%) a6U foil in a cubical Be re-ffector was ueed to eetabiish minimum criti~aI mane measure-ments. Three core sizee, of baeee approximately 8 in., 6.5 in.,and 6 in. square, were made critical by adjusting core height.Reeufts of ihe expefimen~i study Rre preaente,d. (D. C. C.)

.

J3Q65 EFFECT OF STEEbWATER REI$~ECTORS ON THECRITICALfTY OF LOW-ENRICHED URANYL FLfJORIDE SOLff-TION. JObnSOn, E. B.; Newlon, C. E. (Osk Ridi?e National Lab.,

“ Tetm.). Trsne. Amer. Nucl. 30C., 11: 383-4 (June 1968).Frnm 14th +tnUa] Meeting of the American Nuclear Society,

Tokontb. ‘ See CONF-680601, . 0.

3s599 (K-D-2006) EFFECT OF STEEL-WATER REFLECLTORS ON THE CRITICALITY OF LOW+ NRICHED URANYLFLUORIDE sOLUTION. JoWon,’ E. B. (Oak Ridge Natio~Lab., Tenno); Newlon, C. E. (Oak Ridge Gaseous DiffusionPlsnt, Term.). [1967]. Contrsct Wr7405-eng-26. , 8p. (CONF-660,s01-16). Dep. C FSTL 1

From 14ib Annuai Meeting of the American Nuclear Society, ‘Torontm, C)ntario. ‘

Tbe effect of cnmpnaite refiectora of ~teel and water on the re-activity of singie cyiindera, of aqueoua solution of low-enriched.UOZF2is deecrihed. The results are applicable to evaluation of ‘critical ity safety of shipping containers ancl for verification of

~calcuiatinnai modeie. (D.C.CJ

35605 “ (ORNi4263) CRITICAL EXPERIMENTS FORTHE REPETITIVELY PULSED REACTOR SORA. Kiatner, Q.;Mibalczo, J. T. (Oak Ridge National Lab., Teno.). June 1968.Contract W-740 S-eng-26. 105P. Dep. CFSTI.

A eeries of static criticai experiments has been performed onan sccurste mock-up of the SORA Reactor. SORA ie a NaK-cooledrepetitively rmlsed fast reactor which will be used as a high inten-sity neutron aouree for time-of-flight experiments. The reactivityof this reactor 1s varied by a movnbie reflector. Those parameterswhich are rciatcd to the kinetics of the reacior have ken inve6ti-gatrd thoroughly in the critical experiments. They havv been mea-sured fur beryllium w-d for iron rcfktore of several eizcs and forva rloub core and fixed rcfleckm configurations. ‘1’hcMa] rcac -tivitv of the movable refiuctorti varied from 3.7 dollure for aII-cm-wide iron rcflcclor to 12 dollars for a 26.2-cm-wide bcryi-Iium rcfivctur. ‘Nw reactivity of the movni]ie ruflcctor as a func-tion of Itn p)hition hus hucn dwwn w have n pnrabu Iic dtqxuuivnction pcmillon charaetcrizwi fJy the paramc!tcr ax which varimi frum4 to 9.9 cents/cm2. Thu prompt neutrnn time decay is dcscrikfby a fast dcctiy consfani which varlcd bciwtien 0.3u and 0,55 pace-iand a miow decsy conbtant which varied between 0.U5 and 0.10psce-l. The critical mat!ncs fur the various experimcnlti wna be-tween 50.3 to 57.3 kliograma of uranium cnrichcd to 93.2 wt %‘3:U. Unlng space indufxmdcmt ncutmm kinetlm with onc ticluycdneutron group, it hun IJCWNshown that wfth a 24-cm-htgh, ‘7-cm-

thick, 21-crn-wide beryllium reflector the assembiy wlli produce

33050 UNl{iWLKCTftD PLEX10LAf3-GilAly iiil’E-URANIUMpoises approximately SO ~aec wide ●t haif maximum power with a

Ciff”rlCAL MEASUREMENTS. lioogterpt J, Cariton (bepeak-to-minimum power ratio of afqmoximately 4000. (auth)

Alantmv Scientlflc Lnb., N, Mex,). Trans. Amer. NUOL SoO.,11: 389-90 (Juo0 1968),

From 14th Annual Meeting of the Americah Nucieer society,Toronto. See CONF.G80601.

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1968

35657 MASURCA 1-A AND 1-B-PRELIMINARY RESULTS.fpemser, J.; Ilarberger, M.: Bruna, J. G,; Brunet, J. P.; Moug-rdot, J. C.; Schmttt, A. P.; Verrlere, P. (CEA, Cadaracfhe,France). pp 3-33 of Fast Reactor Physics. Vol. 11. Vienna,international Atomic Energy Agency, 1968. (In French).

From Symposium on Fnst Reactor Physics and Related SafetyProblems, Karlaruhe, Germany. See STi/PUB-165(Voi.2);CON F-671 O43-(VO1.2);

The ,MASURCA fast-neutron critical t’nodel at Cadarachc wentcritical in Dcccmber 196G with a plutonlum configuration, usinggraphite aa d{iucnt so as to ohtnln a ncutroh spectrum iyingwlthln ihe spectrsl range of high-power fast reactors. The con-struction of the flrai core. eompnsed of the MASURCA 1-A latticeusing a U -Pu -Fe alloy wlttt 2s’X Pu, and cxpcrlmcntal techniques ‘are described. Speairal index mcasuremont data and reactivitycoeff!clents for various matcrfala are qwrtcd. The materiaibuckflng value of the assembiy was deiermlncd experimentallyueing sp.atiai distributions for varlcms reaction ratea. Somemrwourcmrnt data nrc comparwi with the corrcspnndlng theo -rcllcal vnl!wn rxlmalaird from trannpnri ihwrry or by & MonteCar 10 mcit!,,d. The (JIIRISH(If errfjr and improvcmente which@hollld bc mwic in o.rporlmontal mcihode and In {interpretation ofthe mraauremrnts art. dlr+mmncd. (auth)

44874 (NASA-CR-72329) CAVITY REACTOR GAS-CORECRITICAL EXPERIMENT. Kunze, J. F.; Masson, L. S.; Pin-cock, G. D.; Wood, R. E.; Hyland, R. E. (Generai Electric Co.,Idaho Faiis, Idaho. Nuclear Materlala and Propuieion .Operatlon).Nov. 6, 1967. Contract C-67747-A. 21P. (CONF-671102~42).

From 15th Conference on Remote Systems Technology nndAtom Fair, Chicago, IiL

A gaseoua UFC core configuration was made critical in a 4 foot ‘diameter, 43 inch long, lank and critical ioadlng mcaeuremenisMere made. The resuits from the real gas configuration are com-pared with those from a mockup U-foli configuration of the samedimenslone. It is conciuded that the mockup providea an adequaterepresentation of the gaa core and can be ueed to simplify etudieoof variations in materials and geometry for the cavity reactorconcepi. (H. D. R.)

18570 EXPERIMENTAL AND THEORETICAL 1NVESTIt3A-TIONS ON THE PHYSICS OF FAST REACTORS. ~eipunsklI,A. f.; Abagyan, L. P.: Pnznzyants, N. O.; (and others). pp 445- I91 of Fast Breeder fleactnrs. Evans, P. V. (cd.). Oxford, Per-gamon Press, 1967. 0

From British Nuclear Energy Snciety Conference on FastBreeder Reactors, London. See CONF-660502,

A reactor of the BN-350 type wae studied by tie use of criticalas~emblies with two enrichment zones. Criiical parameters werecafcufated and cru8B section ratios meaaur,ed in the center of theassemblies. Perturbations caused by different materiaie, includingzJ~u, Ta, Re, Fe, A%, Mo, and W, were investigated. cOnkd rodeffectiveness was studied and heterogeneity cffccte analyzed.Prompt neutron iifetime was meaeurcd by means of iwo enr{chedBF, pro~rtionai cormters. Neutron propagating in U02 and iheDuppier effect in a~f-l were etudled. Space-energy neutrn~ dis-tribution in the thick oxide bianket of the BR-1 reactor wns mea-eurcd. Some probieme in calculation theory and methqde aredescribed. inciuding ihcoriea of neutron propagation and tranefer.(L!K)


33063 CHITICALITY OF PLUTONIUM N[TRATE SOLUTIONSIN Sf.Af3 GEOMETRY. I,loyd, R. C.: C@yton E. D. I Hansen,L. E. (llrookhavcn National Lab,, Uptmn, N. ~.). Trana. Amer.NuPI. SoC., 11: 381-2 (June 1968),

~rom 14ttt Annual Mectlng of the American Nuclem Socttiy,Toronto. See CONF -680601. .’

16289 (ORNL-TM-Z082) Ci71TiCAL EXPEillMENTS WITH .FYI{P7HED t’l\Ah’lt”M ~iFTAL-IIOLYE rIm L,kwrz,-pL,HxIf:T.As,\NL~ -TEFLON MIXTllRfX. f.,ln@ugon, il. W. (Oflk ltlI$?oXntlunal Lnb., Term.). Feb. 1968. Contract W-74~5-cng-Jfi.3Pp. Dep. C FSTI.

Rcficctcd and unreflected criilcaf experlmonts were performedat II ~~3LIatom{c rntioa from O tn 5 in mxtnnguinr freomctry withinycrR of rnrlchcd urnnium and Poiyt?thylcn,e. Baec dfmenslona ofthe ansembiics were 5 x iO and 10 x 10 in. In rjomc unrcffcctodrxperimcnts. the mctai wns intrrlcavt!d with PicxiginrI nnrf withTcilrrn at only Uw lnttcr hasc dimcnbions. ilcterogeneity cffl”ctt!wer,: found to &. smali frnm expcrimcnta asscmhicd from thennme or nppmximatciy the tiamc matcrlaie but with differentlnyor thicknrssrs Vniues of k,(f, cnicuiated with the KENO MonteCarlo cork. are in exceiicnt ngrecment with ihe experimentfllvnlum Ry cquatlng gcomctricai bucklinge for rcctnnguinr andsphvrlcni geometry. ihesc dnia were converted to criticai mneseefor Rphrrcs.. Compnrleon8 of the ?xpcrimentaf vaiuea were made tothr criiical mnsses cafcuintmf hy the ANfSN transport cndc forhomngcnrwuo <phcrea. (auth)

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33064 CRITfCAL EkPERfMEf’/TS AT H:USU RATIOS FROM,0 TO 5. Magnuaon, D. W. (Oak Ridge Nationai Lab., Term.).Trans. Amer~ Nuci. Sot., 11: 383(June’ 1968). ,

From 14th Armuai Meeting of the Americ~ Nuciear Society,Toronto, See CON F-660601.

6108 SUPER PROMPT CRITICA”L BEIfAVIOR OF A URA-NRJM-MOLYRDE.NUM.ASSEMBLY. &fhlczo, J: T. (Oak RidgeNatlrmal hb., Term.); Lynn, J. J.; Wateon, J. E.: Dickinson, R. W.Trana. Amer. Nucl. Sot., 10: 611-12 f?Wv. 1967).

From 15th Conference on Remote Systems Technology andAtom F?ir, Chicabm, U1., Nov. 5-9, 1967. See CON F-6711O2.

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14267 EXPERIMENTAL REACTOR WITH GASEOUS UFt.NO. 1. THE CALCULATION OF THE CRiTICAL MASS. Ogusbi.Terumune (Chuo Untv., Japan); Yumoto. RYozo. ChuO D~gfiRikogtiubu’ KQIo, 6: 125-33 fDec. 1965). On Jap~ese).

The criticai rnaas of experimental reactor with gaseous UF8 isdetermined. The reactor was a partiy heterogeneous type, with aBe metal moderator and a graphtte reflector. The core nf the re-actor was of cyiindrtcal shape, 116 cm in diameter and 109 cmheight. The Be moderator waa in the form of tubes of 4.0 cmsquare in cross-section..Gaseoua UF6 wts fiiied in 14~ chnnnciaarranged in a aquarc laUice with 8.0 cm piich. Aiuminum tubcaof 4.0 cm square in cross-section and 0.1 cm thick were used tomake those channcie. The aide refiector was 50.0 cm ihick, nndthe upper and ihe iower reflectors were both 60.0 cm thick. Fromthe rcaults of t hc calculation by one.group theory of four factorformuia, tt was shown that the reactor can reach criiicai masswith that of 2.3 kg 90% enrichdd. UF6 at 0.9 atm. and 80 ‘C. (autld(NSA of Japan) ‘

11

Critical Experiments:19683881 (NASA-C f&722i4(Vol.1)) - CiVi~Y--REA~TOfi CRIT-ICAL EXPERIMENT. VOLUME 1. Final Report. Plncock, “G. D.; Kunze, J. F. (Gem.rssl Electrlc Co., hlaho Falls, Idaho.Nuclear Materlala and Propulsion Operation). Sept. 6, 1967.Contract C-67747-A. 380p. Dep. CF’STI.

A aerlea of experlmehta were conducted at the Idaho Teat stationon a large “cavity ), reactor conaistiW of a cavity 18$ cm in di~-

eter of 122 cm long surrounded by 91 cm of heavy water. Thecavity was fueled with urmrium-235. Monauremtinta were made onvarious conflbwr~tlons, including such vtsrlntlona ao fuel diameterand shnpc, tmrylllum baRlce In the rcfluctor and lsraertlon of ,varloua structural and upcratlng matorlalrn charactoristio of anuclear rocket ,rtiactor. 11 rofertmcea. (auth). . .-

6123 A COMPARISON OF CA~UI.ATION AND EXPERI-MENT FOR ZPR-3 ASSEMBLY 48. Pftterle, T. A. (AtomloPower Development ~ssociates, Ino., Iletrolt); YamamotO, M.Trane. Amer. Nucl. Sot., 10: 530-1 fNov. 1967). .

From 15US Conference on Remote Systems Technology andAtom ~air, Chtcago, XII., Nw. 5-9,,1967. See CO,~F-671102.

,2S075 (APDA-201) CROSS SECTION fiVALUATION kCRITICAL EXPERIMENT ANALYSIS FOR FAST REACTORS.Pitterleo T. A.; Yamamoto, M. (Atomic Power DevelopmentAessoclatee, Inc., Detroit, Mlch.). June 1967. 10lp. Dep. I

For Edison Electric Inst., New Yor~A neutron cross aectlon evaluation end critical experiment aeal-

~els conducted frs support of P@ core rstudiea for tbe EnricoFerret Rettcbx are presented. Cross aecilons of primary impor-tance for faat reactor xaralys le were evaluated for use with theArgonne Natlonts{ Laboratory (ANL) MCZ code which generatesmultl~roup dnlst from bssn~c cross section data. The resultlngmulllgroup rrosn !wctlone were usml for dlffuslon theory cxicu-Inlkmm of ZPR-flI Awuvnbllos 47 and 18. A comparison of ral-mslnl Inn with cxporlmcn! Is preoented for these crltlcal mrl-msmtn. (nutIs)

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35344 RE-EVALUATION OF 2SSU,2~$U, AND 2i8Pu CROSS- -SECTIONS BASED ON MACROSCOPIC AND INTEGRAL DATA.Rakavy, G.; Reisa, Y.; Samoucha, D.; Yeivln, Y. (Rebrew Univ.,Jemealem). pp 255-66 of, Faet Reactor Physics. Vol. LVienna, International Atomic Energy Agency, 1968.

From Symposium on Feet ReaMor Physics and Related SafetyProblems, Karlsruhe, Germany. See STI/PUB-165(Vol.l);CONF-671O43+O1.1).

A generalized least-squares methcd to lfirove microscoplocroaa-section evaluatlona by meana of Inte ral data wea applied

ito re-evaluate the croea asscttona of “U, 2s U, and ‘a%+ UE1OScritical- ma as data of 24 simple metaltlc aystema composed ofthese Iaotopea. It was found that, after some minor modification-of the orlglnal croaa dectlon s!et, most of the experimental inte-gral data could be reproduced. The croeasection modlficationo,as a rule. wem of the order of a few ber cent and well wlthtn theuncertainties In the c roan-sections. The exceptfon to the mle waithe atpu fletilon cross aectlon 12sthe ene~ range up to about 150

ikeV, which had to be deoreasied by 15 to 20 . This reeu[t Issde-pendently confirms the recent meaaurementroof White et *1. (autlri’..-. .,,

Reasonably Homogeneous‘1OO69 THEfJRETICAL ANALYiE9 OF HOMOGENEOUSPLUTONIUM CIUTICAL EXPEIUMENTS. Rtchey, C. R.

. .@sttelle Memorial Inst., R1cbtand, Waah.). NucI.’SC1. Eng.,31: 32-9(1968).

A computational analyelo was made for the large number ofavailable critical experlmenta with hydrogcnous mixtures. Thecalculatlona were made using both multlgroup S, and dlff us kmtheory WIUS18 energy groups obtained wlrh the GAMTEC-11 code.Resonance capture by the, Ieotope “0Pu WSIStreated in the ~R @NRfA spproxlmatlone. The results are given as a parametriceurvey for Pu denssltlos ranging from 0.015 b 1.0 g/en,). Thecalculated mhlmum crlticd maes nf aStPu 18 S47 g for water-refiectwl aqueoua PU(NO$4 aolut[ons end YJ1 g for aimller mtx-turea of 231Pu and water. 14 references. (autb)

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(BNWL-601) REACTOR PHYSICS DATA FOR THEi~fl~zAT*oN oFPLu-roN*ufd IN THERfdAL POWER REAc-; TORS. Schmld, L. C.; Leonard. B. R. Jr.; Lllkala, R. C.:J Smith, R. J. (&lattelle-Northwest, Rlchtmcf, Wash. Pacific b

i Northwest Leb.). May 1968. ContrsAt AT(45-1)-1830. 143P.Dep. CFSTI.

Experimcntel reactor phyelca data have been and arc currently. being obtafrrcd In the UnItcd States to study the utilization of pluto-

nlum frt prosmrt-day thermal reactors. A refercnco for what dataexlet and where It can be frond Is prceented. Ref$?rences to detsfor lattices moderated with 1110, D20, and graphite are fncluded.However, discueaions are centered around the uae of plutonium inH20 reactora because theee reactor types are of most lnteresst inthe United States. ProbIems connected with calculat fng H20-plutortlum systems are flluetrated uafng the data, and areaa are ~.mentioned hi which neede for additional data stfll exist. Crossecctioha, criticality, reactivity coefflclente, kbretics, and burnup&ta are referred to and conclualons are made about the uae ofthe data in evacuating meihods and cross sections for H20 mod-erated reactors. 391 reference. (msth)

-....6113 ANALYSIS OF SOME ~~SU-GRAPHITE CRITICAL EX-PERIMENTS. Sehgal, Bal Raj (fkeokhaven National Lab.,Upton, N. Y.). Trans!. Amer. Nucl. Sot., 10: 535-6 fNov. 1967).

From 15Ur Conference on Remote Systems Technology andAtpm Fair, Chfcago, 111., Nov. 5-9, 1967. See CONF-6711O2.

B 32997 EXPERIMENTAL COM PAR190N OF ifAST- ANDTl\liRMA L- NfillTRON i3UCKLtNGS iN A CRITICA I. AS\t,MBL~.SJuIw, Nobert A. fClarktson Cull. of Tech., Ihtu&nt, h. Y.);Clark, Duvid D. Trat2a. Amer. Nswl. sec., 11: 4u-gl.fuI,~ l~@.

From 14th AMIMi Mwiing of ihe American Nuclear amlcty,Torodiu. - .Sce ~ONf%680tiIN.

[33s)8s)~ ANALYSIS OF A SET OF HOMOGENEOUS U-H20SPHERES. Stauh, Ainn; Harrln, D. R.; Goldsmlth, M. (Westingh-ouse Elcctrlc Corm. Wcet Mlfflln, Pa.). Trnns. Amer. NUCL~&c., 11: 305-6 (Juie 1968).,. From 14th Annual Mectlng of the American Nuciear Society,, Toronio. Sce CON F-660601.. . .

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1968-20410 [G.\ -8$66) NEUTRONIC MEAS[)REMENTS”lN f40N-(“1{1tl(’AI, ?.lI”IIIA. Str.vrns, C. A. (Gulf General Atomic, Inc..Sln Iht.go. (’tllf.). [1967]. Cnntrnct AT(04-3)-167. 34p.(t.{ JSI .GsII.u17-1 !1). I)o\!. c FSTI,

1’1c,nt :ml t “,mf,. rvncx. on Neutron Cross Sections nncf Tech-tx,h>~, t~,lslllngtt,n, 1). C.

%} crsl t}prs of subrrttical cxperlmrnts that arc Intcndz-d toprovklr Intcgrsl cherks O( cross ecct{ons nnrf computational meth-ods In f,wl rcw-!ors nnd [IIst rwutron shicldlng aro dlacusscd.Thrsc lnrlurfc studios of thv time r“cnponse to n pulsed neutronnourrc, stvnzf} -slate ncutrrm vpcctzum men8urcment8, and tran8-rnlsslon mr-azwremrnts. T}!(s methods which nre used to analyzethose mprrlmcnts nre descrllwd, with the cmphnsia plarod onu hnt rrom srction information can be extracted from thcm. Adt, e,. riptlon of how crwe,c wxtlcm nveraghrg proccdurcm are actuallyprrformwi In some of the more aophiatlcnted codes denlgncd forthis purpnsc Ii Inrfurfcd. (nntfr)

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6117 CII lTI(.,\ LITY OF 2ss(1 AQ[?IXX.M NITRATE S( >LIITK)NIN l{KFLE(”TKI) AN{) lTJRl; FI,F.CTEll ARtiAYS. Thnmns,J. T. (tkik Ridge Nntkmnl lflt~., Tmm,). Trana. Amer. NucI.sec., 10: 538-9 fNov. 19r:).

From 16th Conference on Remote Syateme Technology andAtom Fair, Ctdcago, fU., Nor. b-9, 1967. See CONF-6711O2.

1564 (ONNL-CDC-2) CALCULATED NEUTRON MULTI PLf -CATION FACTORS OF UNf FORM AQUUXJS SOLUTIONS OF ‘SWAND 23%. Webster, J. Wallace (Oak Ridge National LatJ., Tern.).Oct. 1967. Contract W-7405 -eng-26. 39p. Dep. C k’STI.

Computatlona of the effective neutron multiplication factor ofsingie units of aqueous solutions of 2SSU02F2and 2J6UOIF2 orereported for guidance in the specification of \ imits applicable toprocesses, such aa storage and transport, for these fissiie lao-tope8. Graph8 are presented of Iqff rIs a function of such param-eter as the mnsa of fiasile material, thu chemical concentra-tion, the tiimenaions of spheres and infinitely long cyiinriers, andthe thickness atid areaJ deneity of infinite slabs. Transporttheory (DTF) codes In the S,, appraxlmation with Hansen– Roachcross sections were utilized and the results agree with relevantexperiments to within 0.01 in kcffi (auth)


4118 THE NUCLEAR 94FETY OF AQUEOUS SOLtiTIONSOF 22.$uAm 2SSu, Webater, J. Wallace (Chk Ridge Natiooalf.ab., Term.). ‘hana. Amer. Nucl. Szc.,10: 539u40v. 19137).

From 15tfI Cmrf.rcnceoo Rem[jtes>atemT&~olo~andAblm Fair. ( NIU:,SI,. 111., Nov. 5 9.1967. See CcjNF-67111)2.

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II. CRITICAL EXPERIMENTS

Lattices

1967

12232 ;f3Aw-3647-2) ~HYSICS VERIFICATfO-l pROi3RAM.Quarter! yTechnical Report No.2, July+ eptember 1966. (Bab-cock and N’iicox Co., Lyrrchburg, Vs.). Nov. 1966. ContractsAT(30-1)-3647: 41 L2007(RDE-1526). 71p. Dep. mn. CfWTI$3.00 cy, $0.65mn.

The results of ckltlcal experiments on cores IV. V, atid VIaprepertcd. In ail assemblies the basic Iattlcc conslstcd of 0.475-inch-nD reds of 2.45’%-enriched U02 akraycdonasquarc pitchof rI.6\! inch and modexated by 1120. The water was peisoned ,with !1,11(], fal~out 1.5 frm-fl.’ll to obtain critical assemblies ap-prnxln)aiclyS feet Indlamctrr. The reactivity worth of Ag-lrt-(’4 control pins arrangrd In configurations typical of pewcrreactors was measured in these cores. The results of mea-mrements of pa, the modiffed conversion ratio, and the eplther-mal neutron spectmm are also reported. (auth) -

35565 fBAW-39”3-10) THoRIUM FUEL &YCLEFORHiAVYWATER MODE RATED ORGANIC COOLED REACTORS. TechnicalPrcgress Report No.7,0ctober 1966-Msrch 1967. fBabcock andWilcox Co.. Lynchburg, Va. Atomic Energy Div.). Mfiy L967.Contract AT(36-1)-393. 18p. Dep. CFST1.

Work directLy relatfng to the thorium–HWOCRdeatgnanddewlopmenlws closed out. Assis~nnce waagiventothe Eval-uated Suclear Data File Task }orce at Bmekhaven. Thle, in-cluded supplying nuclear data ior 2~U, 232Th, and lumped fiesionproducts. Evaluatlonworkwaa done on. varioua reactor conceptsbeing considered. (M. C. G.)

27730 ANALYSIS OF GRAPHITE MOD fiiiATED U’RANHJMAND PLUTONIUM/URANIUM OXIDE FUEL CLUSTERS USINGTHE LATTICE CODE WfMS. Barclay, F. R. (Atomic EnergyEstablishment, Wlnfrith, Eng.). J. Brit. Nucl. Energy Sot., 6:155-60 (Apr. 1967).

The pt$rfe’rmance of the lattice code WIMS waS studied by theanalysis of graphite moderatrd cxpf.mential experiments fuelledwith clusters of U02 or Pu/U02 rodq at tempcratu’rcs up to 39@’C.Earlier work on single metaI rod systems showed that the bestagrcrment in reactivity between U and Pu/U furl was obtsincd by“sing a 2Jg~ ~ VaIuC of,2.0!36 (at 22OO m/s). The use of the IAEA

recommended v of 2.114 In the work showwt a significant depen-dence of reactivity on 23qPUenrichment, which was largely re-moved by using an v value of 2098. (UK)

15764 (CONF-660221-, flp 2S7-90) ANAL+SfS 0; UNIFORMLATTICE EXPERIMEN’rs WITH, THORIA-URANIA FUEL fNHEAVY WATER AND LIGHT WATER AS MODERATORS. Bhatla,H. K. (Atomfc Erdmgy Establishment, Trombay (India))L

The METii USELAii -1 and CAROL codes for Th~ -2a6U(+ or’Th~ –ZS3U% latllces with heavy or light water as moderator wereasse8sed. Experi~ntal hucklings were uticd to ctdcul~te thu KeiIfur uniiorm critical Iatticu cxperimonta performed at ArgonnoNational Luboratcwy, Brookhavcm National Laboratory, and thoBabcock and W@X company, (H .D.R. ) ,

25722 ANALYSIS OF “CiiiTICAL EXPERIMENTS Wi’i’H OR-GANIC-hfODERATED ASSEMBLIES. Bitelli, G.; Martitrelli, R.;Orestano, F. V.; Santandrea, E. Nucl. Sci. Eng., 26: 270-6( May1967).

The results of critical experiments, performed with organic-moderated plate-ty~ assemblies containing U enriched to 9@%in 235u, in the zero-power reactor ROSPO, are reported. Severalcores, differing in critical radius and in ratio of U -to-stuimfcas-stecl plate number, have been investig~ted. The comparison withthe reactivities calculated by a standard two-group calculationprocedure shows an overestimate of the kcf~s with a systematitidependence on the core radius. A satisfactory agreement is foundfor large-size cores. It is. shown that etmple calculational im -pmvements, such as a four-group evaluation of tbe nuclear con-stants, and a more detailed treatment of core-radial reflectorinterface zone, lead to a homogeneously good agreement uverthe whole range of core dimensions. (auth)

15

1967

3Q249 (A14#-7203) “HIGH CONVERSION CRITItiAL’EXPERI-MENTS. Boynton, A. R.; Baird, Q. L.; PlumIce, K. E.; Redmen,

. W, C.; Robinson. W. R.: Stanford, G. S: (Argor,me Natlonrd Lab.,Ill.). Jan. 1967. Contract W-31 -109 -eng-38. 81p. Dep.~FSTI.

A program of criticnf experiments haa extended tbe range ofmcumircd nuolear pqrametcra of 1Ight -water -moderated, S1Ightlyenrlchcd, U02 latticea firther into the under moderated regimi.The l{-to-zs~ atom rati,os ib tho cores’ assembled ran ed from

Fatmut 5 to 0.5. Tim initial converaiop ratio, ‘WJ-to-zs U fissionratio, 2S8Ucapture Cd ratio, thermol disadvantage factor, andCd ratios of various matcrinle reported were meaeured in thefull range of lattices; the imckllnge, cr.iti.cai masses, and reflec-tor eavings roportcd were meaaurcd in”We looser aeaemblics.Inforlnation on temperature coefficient tmd control -element andvarloue materiel wor~hs is included. Although the experimentalresults are not compared with caicuiatioos, these results arecorrelated with rcsuite obtained at other inboratoriee withsimilar fuel at higher H-to-2J8U ratios. (auth)

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12246 MATERIAL B“UCKLINGS FOR 1.002, 1.25, ~nd 1.95 WTPERCENT 2S5UENRICHED URANIUM TUBES IN. LIGHT WATER.Brown, C. L.; Lloyd, R. C, flluttelie Memorial Inst., Richhmd,Wash.). Nucl. .~i. Eng., 27: 1O-15 (Jun. 19137). @Nw’L-S4-267).

hfaloriai tnwklings’tmd extrapul:itiun distancern w~,rc measuredfor rncverrd slightly cnrictied U-mctai tube Iutticcs and tulw-in-iubc osaembi iatlices in iigbi water. Thu tubes measured were:

/’I.UW wt ‘~,2s U tmriched U (2.34-in. Oil; 1.79-in. II)); 1.25 wi ‘7,t~iu ~nricht,d U (~.37-in. of); ~,so-inc ID); and 1.95 wt ~ t~$’fJ&n--.

rh.hrd U (2’,28-h2. OD; 1.41-In. ID). ‘The tube-in-iuk n2tscmbIlC’s .nwasurcd wore: 1.002 wt ‘1 2% outer tuhcs (2.34-in. OD; 1.79-in.

‘ ~) conttsln{ng i.002 wt ‘%2%J inner tubes (1.18-in. OD; 0.49-in.R)): nnd 1.2S WI ‘%7S5Uouter iubcs (2.37-in. OD; 1.80-in. fD) con-tnlnitw! 0.95 wt % 2S5UInner tubes (1.lfl-in. Of): 0.48-in. ID). Max-imum hucklings for the tubes were found io lx! 25.00, 47.00, nndn~,nn m-z, ~cspect{vely; and for the tube-in-tuim nescmhlics,23. !,0 and 38.50 m-t, rcspectivclf. f3nscd on the mca~urcmcnt%cril Ical pnrnmcters for us,e fn nuclear safety armlysce were c’sl-culatrd. (nuth)

.. .3071s EXPiRIMiNTi L f3!JCKLfNQ MEASUREMENTS WITH2.1 WT PERCENT fttJRiCIiFI) URANIUM TUBES IN LIGHTWATER. Browm, C. L. (f!ettette- _CiftO Northwtmt Lab.,

Richiand, Wash.): flansen, L. R.: TOfferl H. Trann” A‘Pr-NUC1. WC., 10t 191-~ (June 1967).

From 13th Annunl MccUn~ of the American Nuclear t%ci~ty,.%n T)It-go, CalIf., June 11-16, 1967. Soe CONF-67~602.

38713 TEMPEf&TURE DEPENDENCE OF ‘NUCLEAR RE-ACTfCIN WTES IN A PU-H20 IATTICE. Carver, J. Cl,:Porter. C. R. (General Electrio CO.. Plasanton, Calif.), TrSINI.

Critical Experiments:

ILattices

14091 ~m ~As~E~ENT OF A ~ATu~L ~NIuM.GBAPHITE LATTICE fN RB-1 BY THE NULL REACTIVITYMETHOD. Camii, F. “(CNEN, Boiogim); Ghtiardotti, G. Energ.Nuct. (?dtien), 13: 480-90 (Sept. 1966). .

Measurement of the infinite multiplic$ition constant Is described‘for a naturai U graphite lattice, aimfiar to the old Brookhavenlattice, carried out in the critical aaaembly RB-1, by the null re-●ctivity method. ‘With respect to paat mkawrements of tbic type,tbe experimental procedure sod the interpretation of the reeultswere made mnre conaiatent and complete. The modifications Intro-duced are dimmased in detail. A preliminary asaeaament was alsomade of tk effect of spectrum mismatching. (autfd. .

‘25712 (BAw’-3~47-O3) PHYSICS VERIFICATION PROGRAM,Finai Repm’t. Clark, R. H.; Baldwin, M. N.: P,ettus, W. Q.; Pilts,T. G.: FUcldnger, R. B. (Babcock and Wilcox Co., Lynchburg,Va. Research and Development Div.). Mar. 1967. Contract

,AT(30-1)-3647: 188P. Dep. CFSTI,

. A program to determine the nuclear propertied of water--modekated, slightly ehricited, uranium dioxide lattice8 perturbedby clusters of Ag-fn-Cd po)aon pins and dissolved boric acid isodescribed. Core parameters and conf iguraiiona typical of thoee ‘in water-moderated power reactore were atudlcd. The unper.turbed basic lattice conaiated of 0.475-inch-OD rods of 2.4 G[L-enricbed U% on a square iattice pitch of O,6+2 inch, and coreradii varied from 19 to 65 cm. Boric acid, in comwntrationa from0 to about 1500 ppM, waa dlaqolvcd In the mcderutor to controie)tceaa reactivity.’ Power reactor fuel elemcmta, incorporntbt~clusttwa of Ag-in-Cd puiaon pfna and t~icul rntruciurei material,

owere almulutcwi in the central regicm UCtbu Iurgetit coro. h!t.a -o auremtmts were made of criticai sue, reactivity worth of poison

pinti, buckling, reftuctor Buvings, thermal dlsmfviudoge factor,“ eplthermai uimorpticm in 23SU,convcraiun rutiv, mwtrun nptwtrum,‘ radial and axutl power diatriimtiun, und tc!mpcruiur’. cocfilc !c,nt.

Experimeniai rtisulta of the prngriim, ma’ny of Whl,”il i)avc been re-ported in quarteriy technical rcporta, are prescntuti. fn twmu‘caaea the data buve been re-anuiyzed, and the rcporkxi resultsmay differ siightly frum those reported eorlier (J. i{.1).)—-

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Amer. ‘NucL Sec., 10: 190(Jurae 1967).From 13th Annual Meeting of the American Nuclear .Sceiety,

I

Wn f)tegfr, CalIf., Junp 11-15, 1~67. See CON F-670602.

16

1967Critical ‘Experiments:Lattices

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27731 i?\’ALUATION OI:SOMI[ UNCKIIT’AINTIESIN THECohll)AllIS(>N III;’r\VItltN TIIIOl{Y ANfJ1..XPI:lUMItNT FORRF.(i(l LAl{ I,IGlf”l’ WATK1{ I,AT fTC’I;S. Fnycrs, F. J.; Kem~he~,P. R.: Tfirry, hl. .l. (Atomic Lnrr~y I{::tnl,llsljlllcnt, Wltirith,Kng.). J. l~rlt. Nuc’l. l:nergy Soc., fi: 161-H l(Apr. 19fi7).’

HI(. I,rinrll,xt [acl[,rs Iuflutnc[ng Ilit, sccur:lcyof comlmrlsonsbt,t}vti,o!) tllt(,ry:lnd[,xl]grltll{nt for rt~nllarwat{,r-lnod{.rated lat-tices am, (~xamintxl. I\,vth( USI. of mor~. (Olalmrntc tht.orcticnlm{.th,~lq, th( :~{v:!!rar.v [al IIN IIhyslc.i MCSIIMXISumtl in Iht. iVIMSIntli, o O,Mlt, ls Is41,1111ishr,(lwilh rr~:ir(l III lf:llw)y., fnsl fls. i<m(tents In ~“11. r(.wulan(r <S:IIIIIIYOqIII 21$[1111111Lhf.tnial ,liq.u{, nn.l:Itw f:ir’ll, rs “1”11,.(Iifli(.illl} ,If mnklng cnrr,,ctl[,n,? f[~r II}{.nnn-,,., ,,, 1,1,,(l,. ,,,sI,!, ,, ,,1 II,,. Ij,, x t,, l),,ckll,, K,q j,, f, , Il., { fr,,, h ,,, (s”q,jrc -nwnt. in .IIIsll ,.xl,(m.ntinl rt,r,~ IR I X;IIIIIIMVIxnri t~. v:IllIilty (dn lllli..ttlnl[~ll.i,},lal an:ll\sls d IIIIN t.ff(wl Ie qu(. stkmwl Slli)jf.ct toIhl - llmltnti,,II it. ls uh(wm !hut th(, (.,)rl,l}~lt:ltl(,ntll mtth,wl,q arc SUf-fltlvnllv nrt,l!nto tnall,nv II(,kjrtl,wu t(]hc rondo r<mrf.r’nlrrg thegro~~ rhotut 111’IsIIcs .){ fuml;tin!. t!(o] !mclcnr dnta Ihrtmgh c(,mpar.Isrm of Uw prl,dlcwd rr’activities and reaction rates withcxperl-

. . . . .mrnl l{c~ults ft~r n fti, rltw of V(+ lntticv. h unlrrg lmth ~~itlca[ andrilmwntlnl If’(’hlliclllcs are ~ittn :Irr(l fu;th~~r cr)nlparjs,,n~ ar,.nrarfc for n S(’h$ctlon of oxfwrlml$nlH uRlng II,,th U02 and fJ mc~]fucI. Thc r~wlt~Of rc(iucln~the lt:lkng,.l )yl){,iqt,ning wjth R Intkesocxperimt’nts arc Slsodcscrihcyf. The results uhtalrrmf SUP-”pnrt the nrwf to introduce a mudlflcatlon to tfw rcmmancm integralsfor ?]aUaa computcdfrom fundatrmntal data, and information IS

23715 ““(fIkR-3126.i) MISURADELLA COSTANTEDI MOLTI-PLICAZIONE INI:INITA DIRETICOLIA URANIONATURALE EGRAFITE NEI,L’INSIEME CRITICO RB-1 CON IL METODODELLA REATTIVITA’ NULLA. (Measurement of the InfiniteMultlpllcatlon Constant of Natural Uranium-Graphite Lattices fnthe Rf3-1 Critical Assembly by Means of the Zero ReactlvltyMethdd). GhI Ilardotti, G. (Socleta Nazionale Metanodottt, MIlsn(Italy). Laboratory Reunlti Studl e Ricerche). Oct. 1966. Con-tract 036-64-3 TEG1. 212P. (In Italian). Dep. mn.

Thu dcvclopmcnt of the zero rcact{vlty technique (PCTR) appliedto natural U/graphite lattices and Its comparlsnn with the suhstltu-tlon method arc described. The experiments were carried out inthe critical asscmhly RB-1 at the Montecuccoltno laboratory, Bnlo-’wm. Two acr~ee of mcasurcmcnta were cmrductcd on two latticesdiffering only with regard to the fuel clement, nne consisting nf asuiid 29.2 mm dia rod in a can, the other being a tube 30 mm to 50’mm OD: chwrncl dla 70 mm square lattic.c pitch of 224 mm. ThcaeiatticcR were chosen from thoec tested in the Marius critical as-scmbiy by the suhsiitutlpn method. RL!SU1(Sshow that a consistentand complet,c eiperitiental prncedure has been devised for mea-suring the &O of natural’ U/graphite lattices by rtrcans of zero re-activity mcthnd. The same spplies to the procedure for analyelaof the rxpcrimcntal data. The errnr in (&O—l) Inherent in mea-surement can in our oplrrion be reduced to 2%. This limit wasrcachod In the iast cxpcrlmcnt nn iatticcs consisting of tubuiarclcmwrts. Agrccmcnt proved tn bc grind with the rcsuifa obtained ,by the CEA in the critical assembly Marius. (tr-auth)

provided on a prcfcrrcd valut, fnr tfrc ratio of cjdthcrmal captureto fi.wion in 2~sU. A pltqh-dqxmdcnt error in the faat fjssion factir -.Md a discrepancy In ~emp~$raturc coefficient are idt, ntificd, butefforts to Iaolatr the c’ausc of these errors were not succcesfu].(UK)

15768 (N-66-33021) CRITICAL MASS STUDIES WITH +HENASA ZERO POWER REACTOR II. fI1. HETEROGENEOUSARRAYS OF CYLINDRICAL VOfDS. Fox, Thomas A.: Mueller,,Robert A.: Ford, C, Hubbard (National Aeronautics and SpaceAdministration, Cleveland, Ohio. Lewie Research Center).Aug. 1966. 25p. (NA$A-TN-D-3555). CFSTI $3.00 Cy, $0.65mn.

.,

.......The NASA Zero Power Rcactnr fI (ZPR-11) has been used to de-

termine experimentally several critical cylindrical conftgurationa ,of aqueous fuel solutions that contain heterngcneoue arrays ofvoids. These vnids are cylindrical, are symmetrically arranged “parallei to the axis of the rcactnr, end extend the height of thecore. The etudy covered a wide range of highly enriched aque -ous U02F2 fuel concentration. The apectfic reactor void config-urations consisted of symme’tricaf arrays of 1, 7, 19, 31 !urd 3’7tubes approximately 7.6 cm in diameter arranged in hcxsgnnafgeometry with pitches of 9.652 or 10.9Z2 cm. In addition to thecritical maes and geometry, dots are prcaented on the thermal .neutron flux dietributione in the central radiaf plane, and on thevariation of ‘void reactivity importance with radal position. These ‘“data explain qualitatively eume of the reactivity effecLe aeaociated.with the different void epncinga. (STAR)

35666 (AliCf_-21Wi) CA N[)U=l\LW EXP}.[llMk N’t’S IN 7.1:lI-2. I)Ai{T llf. DUCKLING AND ~jss {)F CWJI.AN’I’ KXI~Fit[-MEN’f’S. Green, It. It.; Kay, ii, E.; Colfntls, C. \V. (.ltmulcEnergy of Cwwfu Ltd., Chaik River (Onlurlo)). MUY1967.4’ip. DCP. CFS’i’L CAN $1.00.

Experiments have been performed in sfmuluted CAN DU- i)LWlattices in ZED-2 (square tirraya of 28-rod UOZc’ius IcI’B tit aalmcing of 2’7.94 cm) to determine (a) the muterml buckimg ofthe iuttice witil H20 or xir ua “’coolant’s, ” and the fiux perturba-tion and reactivity e[tects of removing the H2U cooitint from 50%of thu fuci asacmhl ius in lhrec gcoruct ric arrung(, nients. ‘1hebuckiing for tile Ii@-cooltxf iattlce WM l.i I;ti * O.UIMm“”~. umtfor the air-cnoicd Iuttice 3.940 * 0.03!I m-z. T!w iu9tI 01 cooimrtexperiments indicuted a significantly emnller incre~lse m reuc-.tiviiy when alternate fuei wvacmblius ur altcrufiw IV*Ss O( fuulaasembliea were voided thun when one -haii uf the l~ulce abouta dia wae voided. (auth)

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196738655 (AEcL-2707) WTEGRAL N~UTRON SPECTRUM ‘MEASUREMENTS IN HEAVY WATEW LATTICES *D A COM- .PARISON WITH THEORY. Green, R. E.; Kay, R. E.; Haleall,M. J, fAtomic Energy of Canada Ltd., Chatk River (Ontario)).June 1967. 18P. (CONF-670707-16). Dep. CFSTT. CAN .$1.00.

From IAEA Sympo@m on Neutron T%errnalizatlon and Reactor “.Spectra, Ann Arbor, Mich.

Experiments have been, performed in the ZEEP and ZED-2crliical facilitica at Chalk River to obtain lqformation about iheneutron spectrum in Iatticea of natural U fuel in heavy water “:moderator. Studiee have been made in lattices containing CIUS-tern of U, U02, and UC having D20, air and organic liquids ascrmkmta, all at room temperature, and some experiments withU02 fuel have Investigated Urc effect of changing the coolant tern- ‘pcratur,c. fntcgrril ncitron apectrom measurements that weremndt$ in both the fuel and moderator regions of latiice cells byactivatln foils containin In, Mn, and Lu are described. Therelative ~i61n/5cMn and “~Luf16Mn activity ratios have been com-pared wiih calculated ratios obtained from liAMMER, a multl-group, multireglon integral tranaport theory codo, SOLO, a multi-group, multiregion collision prohnbiiity code anti MULTIGRO, a .muitigroup, two-rcglon diffusion theory c-de. Ilr- nctlvity rntloshave aIso been interpreted In terms of iiwR’cntc,,tf !pllhrrmnfiwirx, r, and olfert ivc neutron temperature, Tn. Fx;wr Imc!lt nwftheory arc compare d for sclcctcd latUcco to iiluatratc tiw rffvct Iupnn the ncutrrm qwctrum nf fuel matc”rial, clunicr gmrmet rv.tvmlant r-nmponition, and coolant tcmpcraturc, (nuth), . . ,

14097 SPATIAL VARIATION OF THE FAST NEUTRON FLUXIN CELLS OF SLIGHTLY 215U-ENRICHED-URANIUM WATfiR-MOflERATED LATTICES. Hsrdy, J. Jr. (Wesilngbouae Elec-tric Corp., West Mifflin, Pa.); Kiein, D.,; Danneia, R. Nuol. ScLEng., 26: 462-71 (Dec. 1966).

The Intra-cell structure of the fast neutron flux was measuredin several TRX lattices with 2SU (n, fiaa[on) &u@Al (n,o) detectors.The Iuttices were light-water-mcderatcd, with cylindrical, 0.3t17-

,fn. -dia fuei rods of eiightiy enriched U. Tho fuel rods werearranged in hexagonal array a, with li2Q: U volume rat io~ of LO,2.35, 4.02, and ff.1. Meatmrqd activation ahapea and integral ftistedviud~ge factora were Compared with calculated re~ults obuinedwith the MOCA2A Monte Carlo program. AgTeement was verygocd, A one-group Monte Carlo calculation and a one-groupCO1li,eion-probabil it y model were found to perform well in com-parison with h10CA2A. (auth)

44944 [N1>-16953) NF:UTftON DIFFUSION AND hfULTl-l,i,lC,iT~ON m REACTOR LA’r’rIcftS. @men, Muhampladli~fiq (tmperial CoIl. of Science and Technology, Londnn (En-

Nuclear ibwer Group).~i;\%#’sis.

SeId. 1966. 376P. MP.

Nrutron flus rtis}ribution and huckfing mcesurcmcnta were madeas a function nf fuel loading in a oubcrlticnl aaacmhly. The mca-summcnta wwrc mndr in a sq~are cortfigpration. Control rod ef -ft!ctivmcsa mrmnurrmcnts were alao made. Reaulfa were corre-iattwi nn the imsis of diffusion throry. Values for k- and B% are ,shnu n as a function of number of fuel clcmcnta; reflector anvingaa, p plotted aa a, function of reflector \hickneas. Arudyals of controlrwi rffccts IQ htimd oh super-cell calculations and tbc hcteroge-,noous theory. fhf. L. S.)

Critical Experiments:Lattices

789s (oRNL-TM-1;66) ivwiIcAf-tiy OF’LATTICE5OF HEAT TR.OJSFLX{ ltEACTOR KXPEi{IhlENT FUEL ELE-MENTS. Jotuwom E. B.; Reedy, R. K. Jr. (Oak hid@ NatiolmlLab.. Term.). July 20, 1966. Contract W-7405 -cng-26. 14P.Dep. mm C F$TY $3.00 C~. $0.65 mm

A sdries of experiments were completed 10 determine the crlti-cai pammeiera of lattiOc.9 b(, irm fu~l elementa, primariiy ingeometries and environmcntn of Interest for transport, atoragc,and chemical dissolution. Arraya of these elements were madt!critical with water and wjth dilute aqueous U02(NOS)2 eolutiOn oftwo concentration (to simulate dissolver environments) as mod-erator and reflector; onb solution conccntraticm wan 3.97 g 0[23SU/1and the other was E.02 g/1. In some of the aiab lattices inwater, sheete of cadmium were plqced bc!twecn rowti to serve asa neutron ahaorber ae they might in a shipping container.. htuth) .

30259 (ORNL-TM-1S06) CRITICAL LATTICES OF FflGHFLUX 150T0PE Ri2ACT0R FUEL ELEMENTS. Johnson, E. B.(Oak Ridge National Lab., Term.). Mar. 201967. contractW-7405 -eng-26. 10P. Dep. CFSTI.

Lattices of High Flux Isotope Reactor (HFIR) fuel elementowere as8embled in order to deter~tne the critical spacing betweenclcmcnte when moderated and reft ccted by water. It was found that

.$seven elements spaced 6.37 in. in a trhwtgular pattern were criti-cat when submerged Seven outer annuli in tbe same pattern wereCritical when neparated 1,50 in., and seven tnner mnuli were ●tb-critical even when lh contac;, (sutb)

..

38714 (. RITICA I. LATTICES OF U(4J+9) hlETAL RODS INWATER. J,dmwm, K. (“. (Cbk f71dge NaUmml f-ah., T@M.).Trane. Amer. Nd. *.. 10: 1~~-1 (J~mp 19fi7).

From 13th 4nmml hlr~ttnu nf Ilw Am!,rtcnn Nuch?nr SocIrtY,San Dtegn, Calif., Juno 11 13, 19G7. See UUNF-G7UG02.

23709 (A ECL-2651) LATTICE MEASUREMEN= WiTH 7-ROD CLUSTERS OF NATURAL URANIUM CARBiDE IN HEAVY IWATER MODERATOR. PART IL NEUTRON SPECTRUM PA-RAMETERS IN A lATTICE CELL. Kay, R. E.: Green, R. E.(Atumic Energy of Canad~ Ltd., Chaik River (Ontario)). Dec.1966. 46P. Dep. mn. CFSTI $3.00 CY, $0.65 mn. AECL $1.00.

Exprrimdrde have ~en.performed in the ZED-2 critical facUityto drterminc In -Mn and Lu -Mn activity ratios at varioua poaitlooain the central CO1lof Iatiices of eevcn rod cluatera of UC in heavywaler moderator. The mcamiremcnta ivera made in square Iatiimsat m-vrrnl pitehoa ualn~ different coolsnt materials. The activityraiioa havo been Interpreted in terms of tbe Wostcott ●pithrrmalIndex r, and e(fcctlve neutron temperature T. , ●nd compred withvalues predkted hy tka Chnik River iattica recipe cda LATR~P.(autfr) o

6833 (I{\v .~19J7) l~LUTohi Uhi hli;T.\L ilihw)i.(1 i ltIA.pAi{T li, Keizktch, N. (Gc’ncrui Eicwtrvc c.u., iftchi~n.i,

,.. .\vakh. Hanford Atomic Produ&Operational. Aug. 14, 1957. ,Contract .\ T(4,S-1)-1360. 8p. Dep. mn. CFST1 $3.00 cy,$~.65 mn.

A study’was made of the ttuclenr safety invoitwd in the disso-lution. of plutonium melnl. The study indicated that the minimumcriticai maas of a ‘plutonium metni - plutonium ewiution ayatcmma} & no iess thn’n thai for the plutonium muial - water eystt.mor homogcne@ solution aysicm, whlchuvcr is ~mnilcr. Tileenrich(,d uranium metal ~ uranium soluiion ,eystcm was ais”studied. Exyriments nre ❑u~c%ted to verify the rkm!iis. tM. C.(1.)

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18

1967

33702 fBhWL-CG1205) PRELlhflNAl{Y CALCULATIONS‘FOR HZO-MODERATED LATTICES OF UOT4 WT. PERCENTPU02 FUEL HODS. Kobayashi, S.; Uotlnen, V. O. fDatttlle- ~,Northwest, Rictdasrd, Wash. Pacific Northwest Lab.). May 17,1967. Contrsict AT (45-1)-1830. 32p. Dep. ,CFSTI.

Phyalcrn calculations, preliminary to expc riments, for deter-mining ceil-averaged lattice constants am presented. Caicuia-tlons were made for 7.65 wt % and 23.5 wt % ‘to Pu Iattioes forthree geometries. AU parameters are tabulated. Cell-averagedmacroacoplr cross sections are ahown as a function of ksiticespacing. Numerical dcsc.riptious are given for each of the ‘40Pucores. The csicuiated thermal neutron energy spectrum is shown.(M. L.S.)

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40351 1 XPfZiUMENTAL STUDY-OF INTERACTION” flf AR-RAY OF Fl>*l I,it SPRERES. Kuvsfdnov, M. 1.; Stslfmrskll, B. D.At. Fnrrg. (lMSI\), 22: 312-13 [Apr. 1967). fln Ruseien).

llre an~ula r rflst ribution of neutrons cmcrgln~ from a sphere ofOralloy-!10 (mctnllic uranium contninlng 907 23SU)and the criticalmass of two interacting sphorea of Oralloy-90 were measured.The followlng assemblies were lnvefitl~ated: a soli(i sphere 13.5cm in dia without a refiector; a solid sphere 15.1 cm in dia with-out a reflector; a solid sphere 16.7 cm In dia without reflector; asphere 18.3 cm In dia with a hole 6.3 cm in dia in the center with-out a reflectnr; and a sphere 16.7 cm in dia with a hole 2.8 cm india in the center surrounded with an aluminum sheli 30 cm in dia.A Po neutron source was piaced outside the sphere at a distance Lfrom the center of the sphere at various angles between the neu-tron detector and the sphere. The neutron muitiplving Coefficientand the average cosine of the angular neutron distribution were de-termined. A neutron eource in the center of one sphere, and theother sphere were rigidly fixed at : distance L. By measuring tfreneutron flux from such a system and extrapolating the data to thecritical state, it was found that the criticai distance L was equsl.tola.3 cm and L = 25 cm described above. fTTT)

38672 fWCAP-3726-1) PuD#f32 FUEI.ED CRITICAL EX-PERIMENTS. 1 earner, R. D.: Orr, W. L.; Strmr, R. L.: TRYIor.E. G.: Tobirt, J. P.: Vukmlr. A. (Wcstlmgh~se Plectrtc COrP..plttshurgh, Pa. Atomic Power f)lv. ). JUIY 1967. Contract AT-[30-1)-3726. 1290. Deu. CF5TL

A srrirs of critical experiment using mlxcd-oxidp ( PUOZ-U02)plutonhlm fuels wasI carrird out at the Westinghouse Rvactor fZval-untion Ccnt~r (IYREC). Two plutonium fuels with a variation inthe ‘toP, isotopic content and one low enrichment uranl,!m furlwere uFod in an rxperlmcntal program which inciucfcd buckling,rcnctivify, nnd power distribution meaeuremcnte. Buckling mca-eurcme,lts were made in five clean lattices with the 8’3 240Pu fueland two rlcan lattices with the 24’%240PUfuel. With the 6% 240Pufuci, buckling measurements were made in two latticea at two dif-ferent bmon concentrations. The reactivity worths of voids, waterhoics, and controi rode in different teet arrays were determinedin single and multi-region cores. Water hole and water siot powerpeaking effects were measured In clean and berated cores. Powerdistribution measurements were made in cores containing con-centric regions of the diffrrent fuels, multf-region slab cores. andin corcfl containing interapcrsed fuele. (auth]


Lattices

38725 ANA LYSIS OF CRITIC~bFUEL+30 LfJTION RmC-Tf)RS CONTAINING ARM Y3 OF VOID TUBF;S. Mayo, Wendell(Lewis Rcacarch Center, Cleveland). Trans. Amer. Nucl. Sot.,10: 232(June 1967).

From 13th Annual Meeting of the Americnn Nuclear Soclefy, ,~m I)imzo, ~nllf., Jlme 11.15, 1967. .Sm. CON F. fi70602.

2879 FEW GROUP DIFFUSION CALCULATIONS OF ALIGHT WATER MODERATED LATTICfi. MIzuts, Htroshf;Makino, Kafcuji. J. Nucl. 2A. Tectuml. (Tokyo), 3: 309-19(Aug. 1966).

An analysis waa made of a light water mudcrated iattice baaedon few group diffusion calculation. The lattice under inv(, siiga -tion corwiaic.d of 406 fuei ruds in a square lattice armngccf m acylindrical core of 22.46 cm effuctive rasiius mat 127.2 cm corehkight, with a water to fuel voiume ratio of 2.918 The fuel was2.02% cnrichcd U02, clad in 0.6 mm thick Al tube. The thqorcti -caiiy calculated values fbr thermal, ei)ithermai and fast mwtronflux 4Jistritmtimsa, as weil at4 the effective multiplicntlon constantA of the iattice, w$re comi>ared with experjmcntul dtitis. After de-tailed analyaia of the prublems encountered in the COIImu of thestudy the value of 44.9935 was (iutcrmim.d fur A. Uncc. rttiinly in the~,!!(”lear data for fast neutron~ wuuid aljljf.ar to co”siltute t})e

I:rl’atr$it factor of error In A. Thc disrr,,lv?nclcs bctwr,n the’cal -{wlxlcid nnd cxpcrim(, ntal nctlvnt ion distrlhutl~ms of th,, th,, rmal,rl]ilhrrrnal nnd fnst neutrons amount t~)alxnst 2(J, 10, anti 1~’i..rcspoctlw?ly, in thr rcflr$ctnr rc~lon adjolnin~ the core. Tim factthnt these d{tscrcpancics cannut ho removed hv mul?igroup P,calculations wouid point toward insufficiency. of the diffusion orP, cnlcuiatlon In fhis rcgicm. (auth)

2U19 (UCRLSOl~5) SUMhlAiY REPORT OF-CRITIC~LEXPERIMENTS PLUTONIUM ‘ARRAY STUDIES, PHASE I. Mor-ton 111, J. R.: Pierce, G., A.; Gardner, L. L.; Bali, C. J. (Cali-fornia Univ., Livermore. Lawrence Radiation Lab,). Dec. 2201966. Contract W-7405 -eng-48. 56p. Dep. mn. CFSTI $3.00Cy, $0.65 nmo

A series of smsli-scsle 3-dimensional arrays of 3~kg cylindri-cal cr-plutonjum billets was etudied. The parameter meaaured wasdse surface-to-surface spacing of the billets at the criticsi condi-tion. The following systems were studied: 23 (2 x 2 x 2) arraysbare, reflected and mederated; 2 x 2 arrays of 6-kg paira bare andmederated; 33 arrays bare and reflected; and 33 arrays containingaeverai perturbations. Multiplication measurements are aiso re-ported for an extensive group of irregular arrays, which wererelevant to the operational safety of the program. (au~)

38720 INTERACTING ARRAYS OF CONTARJERS WITH2331!Sf_)LUT]~N. Lloyd, R. C.: Clayton, E. D. (Battelle-Paclfic Northwest Lab.. Richland, Wash.). Trans. Amer. ‘UC1”Sot., 10: 18&9(June 1967).

From 131h Annual MeeUng of the American Nuclenr society,San Diego, Calif.. June 11-15, 1967. See CONF-670602.

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1967

30245 (AEcL-2593) DETERMINATIoN OF LATTICEPARAMETERS USING A FEW RODS. Oknzaki, A.; Craig,D. S. (Atomic Energy of Canada Ltd., Chalk River (Ohhrio)).hlar. 1967. 83p. Dep. CFSTL CAN $2.00.

A study baa been made 10 determine whether lattico parametersof natural U, heavy water-moderated latticce c:m be obtained ueingas few as seven test fuel rods placed at tiw cwtler of a driver orreference Iattice of known properties. Up io acvcm test reds weresubstituted twcccsalveiy for r~fertnce rods and tbe criticai heightchanges measured. hlc,asurc’mc’nia were made for fuel ciustcrs ofnaturaI U02 and U mctai wiih D20, He and organic (HB-40) cool-ants, In 18 and 22 cm triangular piich lniticce. A two-groupbcterogencoua reactor calculation program (MICRETE) was usedto dcicrminc the bucklingrt of the teat rod lattices from the criticaiheight changea. For D20-cooicd rods the values are in good agree-ment with thuse obtained by conventiortal flux mapping in latticescontaining a large number of ieat rode, even for buckiing differ-ences of 6 m-z between test and reference Iatiicee. The ugreemcid,in worse for He and iiB-40 cooled rodb. Measurementrn were madeof the neutron flux distribution, West.cott spectrum parameters rand T, initial conversicat ratio, and fast fiseion ratio using sevtintest rods and in gencmi the results are in agreement with thosemade in lattices containing a iargc number of rode. (with)

157$1 DETERidfNATION OF UTrICE pARAMETEf@ OFD@-MODERATED SYSTEMS FROM PULSED AND STATIC ?iEtJ-,TRON MEASUREMENTS. Parkinson, T. F,: Diaz, N. J.; Peret,R. B. (Unit. of Fiorida, Clalnsriiie). Nuci. Energ.. 262-TofNoT.-t3eo. 1966).

Experiments are described in which befh tbe neutron die-awaymethod mrf tbe statfo exponwtt@ method, have been ●pfdled to a

cvariety of ttatumi-u, DIO-moderated Iattioek Three differ~nt ~;lanacm-blies were us”ed ~nd data were obtained in botb bare and ,side rcflecied ayeteme. From the rneamt~ed decay constante, ~ _the infinite reproduction conetant, and Bzm, the material buckling,wtire evaiuaied. Tbeoreticai atudiee were made of tbe muiligroup,multiregfon aubcriticai and the experimental decay cons. tunt~ tur“both bare and rcfiected systems agreed wwli with a two- rt.giun,two-group model. From the combined puleed and attitic experi-menifi, tbe dispersion iaw for multiplying media was de.-ived.(auth)

140bl (A E-264) BUCKLiNf3 ktEASUREME~TS ~P b 2tilJE.G C ON iAll ICES OF AOtiSTA CLUSTERS AND ON ~0AIuNE IN ‘Iiik i>itt SSURMfiLi EXPONENTIAL ASSEMBLY ‘M;Pernson, f4.; Andertibcm, A. J. W.; Wiluinhi, C.-E. (AklleimiqfetAlumcnergt. Stnckboim (Sweden)). Nov. 1966. 58P. Ucp. mn.

th,kiing d~tcrminattonu by nwann of fiux mapping were per-fortncd in TZ up 10250 C WI two Intticuu of Agcaia fuei nmwmbiiesin D# muf on ~0 uiunc.Mob; of the flux mcnsuremcntu weremad,. witit flnnlun cuunlcru In pruutiurc thimbles. The purturha-tlona cmm.d by tlm tidmbtta were atudi~d cxporimcntaliy In vnri-aIs ways and comparui witk lwu-grnup diifualon-tiwory caiudn-tiotq. In one of the iatticcs the cffcctivenctirn of n controi red(AglnCd) was also investigatcxi. The remdte of the dfffuhion lengthexperiments indicatud some eyaiematfc error of the order of 0.16-0.10 m-z in the Lrucklings measured, though the temperature de-pendcnce ebouid be wcii eatabliabcd. The Lxmklinga of the twoiattices ●tudid (square pitches ’24 atxf 27 cm) were found to beiem sensitive to temperature than theoretical caicuintiona predict,the temperature coefficient being more than 10% amelier. Thebuckflng changes from 20 to 250 C were abnut -2.4 and -1.8 m+,rcapectiveiy, for the two iattices. Curing part of the experimentalperiod abcut 3d% unexplained excees abaorptinn occurred in theheavy waber. (autb) #


;8666 [NP-16873) EXPERIMENTAL AND THEORETICALSTUDIES OF MATERIAL BUCK1,lNU AND DIFFUSION CCM F’FI-cwwrs m sfNGu:-AND MULTI-REGION t4uc LEAft iwcrortLATTICES. Persson, Rolf (Chalmera Tekntskd iiqfwkcl~,Goteborg (Sweden)). 1966. 15P. Dep.

‘Tfweis.An interpretation ie given to the various himtu d Imckiin mea-

?mtrementa performed in heavy water mode rat cd bxponentia andcritical facilities. Problems connected with buundary transients,anisoiropy, and heterogeneity are discuescd. ‘flw experiments

‘ adapt tu ltiu onu-gruup nnd two-group mudelti; smglc-rcgiun coresrcgartfi!~ higher harmonics, #pectral traneicnhi, and hctcrogcneityeffects in flux distributions; muiti-region cores rt,garding diffrr -enctia in diffusion cocfficiente, slmctral transicnis hctwecn re-gions, and buckling’cquivitlence of control rods. fndivicfual nnalyti-cai abstracts of preprinta appear in Nucicar Scivncc Abstra6ts ●s“NSA 11: 2139; NSA 10: 1576G; NSA lt3: ‘/99! )3; NSA 18. 33035;NSA 19: 17200; NSA 20: 40377; NSA 21: 5677; NSA 21 14001; and

Prcprini No. V, whlcsh, in @nF! to hc pul,iislwti In n rcvlm$ff formin Nuklconik nml will hc alwtrn( trri whrn It .?l!;#srs to pIIIIllc.(Sweden)

,,8101 ORGANIC-COOLED HEAVY-WATER-MODENATED233u-FuELED UTITCE ExpER&f ENT& price, G. A,; Windsor,$4.; ‘fimoey, W.; Hellairznd, E. (BrOOkbaVefi t4attonzi Lab., tfpmn,N. Y.). Trane. Amer. Nucl. SoC., 9: 516-.19 [OGL-N0V. 1966).

19457 (BNL-SOO12j OIiGANfC-COOLED, HEAVY WATER-MODE~TED, 2$afJ FUELED LATTfCE EXPERIMENTS. Prtce,

G. A.; Wlndeor, H. H.; Tunney, W. J.: ffel18trrmd, E. @rook-haven National Lab., Upton, N. Y.). Aug. 2S, 1966. ContractAT(30-2)-Gen-16. 38p. Dep. mn. CFSTI $3.00 CY. $0.6S UM.

Materizf neutron buckiings and thermal flux activation rateswere measured for four latticeo contafhing 2S3Uand Th02 with ~0moderation. Accuracy of the buckiing measurements is essentiallylimited by the ehort fuel length end the smaf.f number of clusteredfuel elements. The METHUSELAH calculations underestimate theflux depreaaion in the clustered elements by quite a large factorHowever, the effect on reactivity is relatively smeii because ofcompqne.sting absorption in the stahdeso steel ctiister. METHU-SELAH nVerestimatee the buckling with a’ corresponding overecU-mate in kem There ia a need for improvement in ihe reactor cal-cul~tiona, althnugh the source of error is not obvious; jauth)

~8659 (BNI.A’003S) UR~ItiM-WATER LA’fT’ICE COMPI-LATION. PART I. BNL EXPONENTIAL ASSEMBLIES. Price, ‘Glerqr A. (Brookttaven National Lab., Upton, N; Y.). Dee. 30,1966. 279p. f)ep. C FSTIO

Tbe Brookbaven Nationai @oratory exponential experimentswith the lattice specifications are recorded for the further devel-opment of theoretical mndels and neutron croes sectinn libraries ‘neceseary fnr tbe design of power reactors. Tbe exper~ment iodetermfne cadmium ratins io described. An appendix summa-rizes some nf the pf, measurements. Measurements of the ther-mal disadvantage factor t DYare accomplished by irradiating smaliDy foils in a fuel red and in water. Thfs technique is explained Inan appendix. A fission catcher technfque ie uacd to measure thefaat-to-thermal fiseion ratio, 6~~. Two techniques for mcneuringmaterfal buckling in exponential an.eemblics are described. Abibliography nf 100 references is inc~dcd. (J. C.W.) . .

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8100 ANA LYSIS $3F 7- AND 19-ltOD UC+ CLUSl+X{ EX’PER1-MENTS WITN THE HAMMER CODE. IUsti, 1[: A. (CombunllonEnglnvcring, Inc., Windsor, Cum).). Trans. Amer. Nucl. SOC., 9:’517-18 (oct. -Nov. 1966). I

12241 (’1{1rlCAL r31M1:tiSl[”)NS01: WATEI{-HEFLfKTfUJSYS ~EMS C’L)Nl’AINlffi 11’11.R20-”r. Huthxfge, G. P.; Lmbtre,F. A.; llr\ce, C. H. (Webllnghimse Electric Corp., Idaho Pane,Itmhuj. Nu{,l. AI@., 2: 4bl-7(I)ccl, 196{,).

( ‘Jl(wl.it,,l i Alut.n of Ih(: extrapnlu[mn dlo[uucu fur wittt. r. rc,flt.cli., i .> II 11:() Zr t(.rndry,tiy~tums :tr~. 1,)cric.nt,.d ‘11118

ex!rdlxhl,tti., ti, ,lIh I,Um., t~,ga,lhur wII}I j)rcvluutrly iwldl>hI.cl (rllicalInmklmk (LIIJ, IA’I rolls tth, d(.let’inln.ilhm uf crIIn.,il dlnumslnurnfor till Ihbsd,lc c.umpI)stlbIIs 01 I)IIs syslt, m, l.mIl[uli tldl.t werepreviously avadab]e for the extrupol~ticm dfstwrce for the ‘~U-1120binary ;ystem, and no d~ta existed for the ternary sy~tem.A qutintlttitivc (Ic,tcrminatifm of (he csxtraprdstlotr dlstanct. wtisachImwd utilizing, in a unique msnncr, nuclc:tr UNICS dcve]opedfar reactor dcsl~n purposes. Accurxcy of the results warn cun-firmmf at cum,jijsltiuns f,, r which cxpcrimtmLil d:tt:t urc svallable.‘f’ke ektr.ip,,latjim dlstimc,c u ;ts fuuml to Im csscntudly mdcpvndwttOf lhc shupc of”[he syslelll IJU1biruO~!y dt!ptisn[!(.fltUpun cumpotii-tion ,\ s)ngl~~ di;q:rurn th:it prv,scnts critical buckling und cxtrapo-lat ion distwvx :1s a funcii(,n of compusiti(,n w~s devll{,pcd. N’lththis dm~rsm it is pussible to determine critictil dimensions fora given shape and compositl[m and tq)timunl cunditicms for criti-cality As an important pr~clicxl exxmple, the minimum criticallimits fur optimally w~t(sr-mr@ratud cylindrical arrays of 17sU-Z~ fuel c.lcmcnts are presented us O function of fuel-element lengthand compusitinn (suth)

40688 MEASUREMENT OF XIATERIAL BUCKLING IN”VAR-IOUS SUBCRfTICAL ARRANGEMENTS OF NATURAL URANIUMAND LIGHT WATER. Schade, Diethard (Technlsche Hoch-schule. Darmstadt, Ger.). Nukleonfk, 10: 54-8(July 1967). (InGerman).

hlatcrial buckling was measured in 10 subcritical arrzmgemknta.The fuel elements consisted of metallic natural U rods 2 cmdiameter; the moderator was light water. Five of the investigatedarrangements were crossed grids, w’hich,formed a Cartesiancoordinate system by superposition of three parallel grids in thethree axial directions, the rrmaining grids were formed byparallel rods in the moderator. The crossed grids yielded asmaller m~imum material buckfing thag {he parallel grids. Theresults indicated that matcrisl buckling can be increased by useof s smaller rod radius. Calculation of materlaf buckling in the “investigated pnrallel grids by methods used for interpretation oflight enrlchrd U–water reactors gave a satisfactory agreementwith experimental vafuea. (tr-auth)


29831 iMIT-2344-08) Tfff? hfEAsUREMfiNT OF REACTORP.+ RAM ETERS IN SLIGHTLY ENRICHED URANIUM, HEAVYWATER MODERATED hfINtATURfi LATTICES. Sefchovich, E.;Kaplan, I.; Thompson, T. J. (Massachusetts [net. of Tech.,Cambridge. Dept. of Nuclear Engineering). Oct. 1966. Con-tract AT(30-1)-2344. 2fJ.tp. (MITNE-76). Dep. CFSTI.

Reactor physics parameters were measured fn six bcavy-wat.erlattices which were mhriature versions of lattices bfvctiil~dtcd ex-tensively In the exponcntt@ assembly at hl. I.T. The l~ttlces con-sisted of O’[email protected] rods br two 2asU concentrations, 11143and 1.027%, and three spticfngs, 1.25, 1.75, and 2.50 fn. “rho follow-.tng quantities were measured fn each lattice: the ratio of cpiend-mium to subca@nium capture rates br 238U (p2~; the ratio of epl -

..cadmium to nubcacfmium fisalon ratea fn 2% (b~d; the ratio uf ihetotal capture rate in 2]8U to the total fission rate fn 235U(C ‘J; the23~-m-2s~u flgsion ratio (152d; the Intritcellufar dlstritJution of the‘activity of bare and cadmium-covered gold foils; and the axiid tincf

‘ radial activity dfstrlbutlorw of baru and cudmlum-covered goldfoils. Corrections dcrlved from ttwory had to be applied to accountfor tie presence of source neutrrma and houndury effects. The age-.diffusion model developed by i~cak WLS improved and correctionswere obtained @ cx.tr~polaw the miniature lattice chin w expontm-tlal, critical, id rnfinllc stiaembllcs. ‘f’o test the vaiidlty of theextrapolailon methods, the results ubLimc!d by cxtrapolatfn~ thominfature lattice data b exl)oncntld aswmbfies wcrr! comlmrcd

‘ with the resuf is of rneasuremcntn nuidc in the cxprmcmilxl ussemhlyat M.I. T. The cxtrtipol~tccl and ntc:isurecf r$sulis agrcc(f gcnemffywitbfn the expcrlmefital errur. It im shuwn ?Jmt t.u cxtrapoixtc tfw

values of p38, 626, and C* rrwanured tn the miniature iatiice tolarger atmemhl fcs, It itI onf y nccctisury to dcticribc theorctlcullythe measured slmti~f rflbtrlbuilk of ibe cadmium ratio of goid.The experimental detcrn] b,uifun uf the matcrfal buckifny, in mfni -ature lattices wati lnvesli~dted. [t is apparent t.ht t.fw Incluslon oftrarmpori effcct~ may be necessary, first, W dcflnc the Intilcrlalbucklfng and, twcond, to obtain Its value. The correction fwiors

for p2S, 62S, snd C* were shown to depend on k- so that k- cwmotbe determined dikcctfy from measurenmnts In the mfniaturw lut-tfce. Ao iterative procedure watl developed to determfne ho which

.“ converges rapidfy and, for the lattfces b3Ve&iLfgiJtCd,icd to remitsthat were to a~mecmcnt with the values of k- ubtitfnwi from mca-surcmenta br the exponwrifat ustmmbfy at M. I.’l’. (uuth)

38717 “ MEASUREMENT OF REACTOR PARAMETERS INSLfGIITLY KNRICIlf’;I) URAN’IITM, HEAVY-WAT}:R- M~~Dl.RATEDMINIATURE LAT’tlCKS. Sefc!hovich, E.; Kaplan, L; Thompson.T. J. frvlar+sachtmette fnst. of Tech., Cambridge). Trans. Amer.Nucl. WC., 10: 194-5 (June 1967).

From 13th Annual Meettng of the American Nuclear Soclcty,San Die@, Callf., Jurre 11-15, 1967. See CONF-670602.

38716 .MI:ASUR1>MENTS hND ANA I>YSI:S OF SOM1. ‘331!+Th($ WAT14:R fATTtCL EXi’ERtMItN”rS. spht~l. [~al ltnl:Windsor, lf. 1{.: Ttmoey, W. J. (Rrookhnven ?.’IIIIIWI I I.. II.,[Tplon, N. Y.). Trnns. Amrr. ~ucl. SfrC., lo: I!).{-’f I.l’II!l”1967).

From 13th Annual Met?ffng of the Amcricnn N!jclcnr *j~ff’tY,San r31eKo, Cfrllf., June 11-1501967. See C(JNF-670602.

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1967

38660 (ORNL-CDC-1) CRITICALITY OF LARGE SYSTEMSOF SUBCRITICAL U(93) COMPONENTS. Thomas, J. T. (OakRidge NatIonsl Lab., Term). Aug. 1967. Contract W-7405 -eng-26. 37p. Dep. CFSTI.

Ilethtmis for eattmating the number of components required forcrittcnIity of unreflected and paraffin reflected systems of sub-critical untts are described. A neutron nonleakage fraction pa-rameter Is defined and leads to a correlation confirmed to within5’1 of the number of units by comparison wltb experimental datafor three dimensional cuboidal arraya. A density analogue repre-sentation of the arraya is readily derivable and is shown to ap-proximate the results from the above methed, but ia less precise.Factors by which the number of units in an unreflected criticalarray ia reduced by adding a parafffn reflector are found to rangefrom about SLYto greater than 30 depending on the material andon the average uranium density considered. The methafa aresupperted by Xfonte Carlo calculatlona demonstrated to be re-liable by comparison with the results of critical experiments.(auth)

30136 (CIA-7934) LATTiCE PHYSICS STUDIES. QusrterlyProgress Report for the Period Ending March 31, 1967. Trtmble,G. D.; Gozani, T.: Nelll, J. M.: Orphan, V.; Preskltt, C. A. (Gen-eral Dynamics Corp., San Diego, Cal If. General Atomic Dtv.).Apr. 11, 1967. Contract AT(04-3)-167. 85p. (EURAEC-lS40).DCP. C FSTI.

Work Performed uNfer United States-Eurntom Joint Research ,and Development Program.

A facility for measurement of neutron spectra in tightly packedlattices wan performance-teeted. Fbll activation analyaea andtime-of-flight apcctral mqaaurcmente were made in erblum ni-trate. k ,,( and dleaway time for the f[rat experlmantal lattice wascalculated. Tho po’eslble use of a pressure vessel for elevatedtemperature measurements.was evaluated. (M. L. S.)

38722 “ EXPERIMENTS AND ‘CA’LCUtiTIONS FO~ H20-MODERATED ASSEMBXJES CONTAINING U~-2 WT PERCENTpu~ FUEL RODS. Uotfnen, V. O.: Willlams, L. D. @atteUe_Psclftc Northwest Lab,, R1chland, Wash.). Trans. Amer. Nucl.Soo., 10: 186-7 (June 1967).

From 13t.h Amual Meettng of the American Nuclear Society,San Diego, CalIf., June 11-15, 1967. See C.ONF-670602.

30257 (M LM-1395) NEU~RON MULTIPLICATION” EXPER~dIMENT WfTH 2a1Pu D1OXIDE DOUBLE SEAI,ED IN CA LORIMETiiRIWESWRf? CONTAINERS. Wolfe, R. A.; Edllng, D. A.; Gieseing,f). F.; Kahle, J, f3.; Stubbhm, W. F. (Mound Lab., Miamisburg,Ohio). Jan. 9, 1967. Contract AT(33-1)-Gen-53. 16P. Dep.CFSTI.

Tho peutroh multiplication of high !sotoptc anatyals PU02 aa-scmhled In v~rloue. planar arrays in both water and air mediawaa dctcrmlnml. TIN! Isotopic dlatrlbution of the Pu was approxi-mately 80% 238Pu, 16% 239Fu, 3% ‘f~po, and 1% 241FW Twenty-onedouhlc-scaled calorimeter pressure containers, each containingapproxi matcl y 130 grams of the ‘aaPu Isotope, were assembledin three planar arrays mmsisttng of 3-tn., I-In., and Yf,-in. edge-to-cdgo spacing. No atgrdftcsnt neutron mtdtlplication was de-tectable in the fully aasembkf 1-in. planar array In the watermedium or In the 3-in. planer array In tbo air medium. A lowmultiplying region (M N 1.026) dtd exist In the !/iC-in. plamr .array but was not large emmgh to be used in reliably extrap-olating ta the crittcal masa of *38Pu. (auth) . ,

CriticalLattices

Experiments:

30334 S[’F3-CRITICAL MEASUREMENTS OF BUCKL04G ‘ANI) NIIGRATION AREA USING SPONTANEOUS F1SS1ON AS TIiE

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PRIMARY NEUTRON SOURCE. Ahmad, M.; RarrIa, M. J. (Univ.:of M.anchcstcr, F.ng.). J. Phys., D, 1: 645-51( May 1968).

Using aponlanecm fiseion as the sole primary neutron source,measurements were made of tbo lattIcc ‘conntnnts of a sub-critical

.

aasembly fuclled with natursl urardum reds of 1.2 !n. dlamotcr nndmoderated by water (Vm/Vti = 1.43). The expcrlmentat procodum1s described and a atmple two-group analyais to developed for in-terpreting the measuremcnta. The tiermsl neutron fluxes worelow, be!ng of the order of 25 neutrons/cm2 e; ncverthcleas thebuckling was determined as -(6.80 1 0.42) 10-$ cm-z, a value tngood agreement with that obtained from conventional exponentialexperiments. (auth) . .

50831 EXPERIMENTAL REACTOR RB-I. CAIJnRAT1014AN,U Ml?ASIJREMftNT OF K FOR A NATURAL UmNIuM LAT-TICE MODRHATEI1 BY GRAPHITE. Aiello, P.; Azzonl, P.;Casall, ~.; (and othern) (CNEN, flologna). PP 341-60 of Flslmdel Rf!attor.a. Rome, Conalglio Nnzlonale delte Rlcerche, 1966,@ Italian).

From Conference on Phyalcs of Reactors, MRan. Sce COfiF.469. ‘

Rca&lvlty mcatmrcmcnta in Rn-1 u@? the Mcrcritlcal Prrleftncthod arc dcacrlbmf; cnlibratlon of tho control rods and contrulsyatcm 1s discuefmct. Neutron flUX meaaurcmentn usfng actlvmarlctcctors le dcscrlbcd. Mcaaurcmcnt Of tnf~ltc neutron mullliil.cation [s summarized; datagre tabulated. (M. L. S.)

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35641 VANATION’OF k–inf WITH COOLANT DENSITY FORA PLUTONILTM-FUELLED STEAM-CODLED FAST REACTORLATTICE. COMPANISON .OF EXPENMENT WfTH PREDICTION.Arnold, M. J.; Fox, W. N.; George, C. F.; Richmond, R. (UnttcdKtngdom Atomic Energy Authority, Winfrith, Eng.). pp 429-50of Past Renctor physics. Vol. 11. Vienna, International AtomicEnergy Agency, 1966.

From Symposium on Fast Reactor Physics and Related SafetyProblems, Karlaruhe, Germany. we STI/PUB–165(Vol.2);CON F-671 O43-(VO1.2),

The design of a steam-cooled fast reactor with satisfactorysafety and control charactcrlstice and an acceptable breedingperformance requires an accurate knowlmigc of the neutron bal-ance and its variation with coolant density. When an mscasmcntof such a system was undertaken the basic nuclear data availablefor use In the lattice calculation wns of Inauffic(cnt accuracy andlittle lntc~rnl information on latt{ccs of the rcqulred compes; iionwas available. A program of experimental mca Nurcmcnte of theneutron balance nnrl Its variation with coolnnt d.msity In lattlcesof tbia t}Tc was therefore undertaken. Meafiurcmmrte of importantneutron reaction rates and of k-lnflnlty were carried out in thereactor DIMPLE at A. E. E:, Wlnfrlth, In, a ema R central fidst re-actor zone drl~,en critical hv a surrounding thermal rcnctor zone.Thl B 8yBtcm produced at ite center the correct fnst sfmctrumwhile requlrlng only 50 kg of Pu In the central fast test zone,Three latt[cca were studlcd in which appropriate polypropyleneplates were lnscrted in a regular array to slmulatc the flocdedcondition, and the operating condltlnn (0.1 g/cmj equivalent steam

,denslty); the wdded condltfon wa8 fitudlcd by rcmovlrrg the plntcs.In nll Ihror Int?lrvra etudlt,(l, Ih* mo~t !m~,rlnnt reart{on rnlcafnfl,!t.nrlni! [he t (,t,lnnt corfflrlrnt of k-[nflnlty were f16Rlnn in7’”1311.tnr.turr In ““II nnd t,, a Ivpavr 0.[011! capfurr In 719Pu. Pnr-tlmllar nftmllnn was thcrrf!. rr palrl to (Iw {Iiro,.t mcapuremcnt ofthonc quantltlrs uhi(.h, !oj:,.fhor with nthrr rclstlvrly unlmporLmttRnslon rnfrta, nrtw!lntwl for RO to !){1’7.of WC tnlnl lntticc nhsorp-[ION. In (mv lnf~lt.r theec mi.nm!rvmrnta wore nupplcmcnt<-1 IJYartlr,.ct mva.,]rrmt. nt of k-lnflnlly to pr,,vl(lc e chock on thr cnlcu-Iatl,,n (If ,Inm.a-j.d rmvtlnn ratrs (nulh)

30338 ZERO-REACTIVITY METHOD IN NUCLEAR PARAM-ETF. REVALUATION OF HEAVY-WATER POWER REACTORS.Baccollni, A.; Casali, F.; Casing, G.: Glacobblo V.; Hage, W.;Rustlchelll, F.: Sturm, B. (CNEN, Bologna. EUf?ATOM, Iepra,Italy). pp 643-530f Heavy-WaterPowcr Reactors. Vienna,Interrmtlonal Atomic Energy Agency, 1968.

From Sympo6ium on Heavy-Water Power Reactors oViema,Austria: See ST1/PUB-163; CONF-670917.

Ascries ofk~mcasurcmcnts by the zero- reactivity methed andby dctallcd parameter dctcrminationa has been carried out jointlyby C,NEN and EURATOM at the R&l reactor of Montecuccollno(Relogltn), Italy. The nlrn of the cxpcrlments was to supply data forthe dcwclopmcnt of the ORGEL-type rmtctnr, to Investigate thefeasibility of the zero-reactivity method snd to test the the reli-abllit,v of the nuclear codds used. The experimental data were com-pared with the same quantities inferred from theoretical cvalua-tlona and with the results of substitution measurements performedat the ECO critical facility of 16pra. Tke fuel elements used werelo-rod uranium metal ,And7-rod uranium carbide cluatera, or-ganic ceolcd. From the experimental snd theeretlcal analyeIs Itnppcared that ~h~ results frOm tbe zerO-reactivity methOd wereconsistent with the results obtained by the other experimentaltcchnlqucs and the theqretlcel calculations. R is to be outlinedthat, in the zero-reactivity cxperimenta, the buffer region wasconstitutml by only 8 ORGEL elements which represents sn at-trnrtlvb ,.conomicai advantage compared with other techniques.Morv[wor, it seems that when small clmnges lo the teet elementsarc Involved. the measurement can be performed leaving thesame buffer region without seriously affecting the accuracy ofthe resuits, (auth)

,


25008 DEVELOPhIENT OF PLUTONIUM FUEL9 AND STUD- \lJLS OF PLUTONIUM RECYCLING IN LIGHT WATER REACTORS.Bairlot, H. (Belgo Nucleaire, Brusseis); Debrue, J.; de Waegh,F.; Fossoul, E.; hlotte, F.i Vanden Bemden, E.; Van LIerde, W. Ipp 335-78 of Development of Light Water Reactore in the Com-munfty. Brussels, Euratom, 1967. (In French).

See EUR-3561; CON F-661 134.Use of plutonium recycle in thermal wpter-cooled power reac- ,

tora. is discussed, economics are considered. The developmentof the fuel 1s outlined; fabrication, nondestructive testing andradiation testing are disastted. Thermal studies and ncutrordcscalculational methods are described. Criticality studies using “~plutonium fuel elements in the VENUS critlcai aescmbly, fissionratio measurements, and neutron spcctrn determinations areoutllned. Afl dats nre tabulated. 35 rcfermices. (M. L.S.)

634s4 (BNWM28) PLUTONIUM UTILIZATION PRO-GRAM. Techntcal Actltitles Quarterly Report, March-May 1968.(Battelle-Northwest, R!chland, Wash. Pacific Northwest Lab.).

-9e~. 1968. 67D. flcP. CFSTf.CRITICALITY”STUDIES- measurcmenta of critical number of

aluminum–plutonium fuel rods in water mnderator, effect oflattice pitch and boron concentration on; microscopic latticeparameter mcasurementa en water-mcderated plutonium ox-ide ( ~C$) -uranium oxide (U(+) rods; measurements nf boronworth pnd conccntratlcm for cold and xen@t-free PRTR BatchCore ,

NE[JTRf)NS-capture-tn-f ission ratio measurements in plu-t(miu m-2.79: rnultirllcatlun flctor dvt~$r, ninati,m In wltcr -m(rnloralml plutonium oxlfir ( IMOJ u rsnium oxide (U~)lnltiCl!S; rrswmnrv w+-apc prrhblllfy tfctcrmlnatfnn fnrumnil!m-238

33r . hlKASUilii MENTS UN LATTICES OF U~-Pu~~. it[X.1CLUa I’fiRS IN i)2{l WI1’i{ QO, AIRO’AND U1{GANIC CWJLAN’~S.Bnurnum!, N. !.; I)eilorin, D. J.; Olson, R. I..; o’.Nciii, G. F.(ii. i. duPunt du Ncmoure und Co., Aikcn, S. C.). lr.ms.AIIN.r. Pfuc$i.SOLo.,i 1: 254-5 (JUIUo1W8).

i“runt 14111.Annu.d Mc~c41nguf tile Amcricun Nuclcur >.8..Ic,!Y,‘ruruntu. Sce (: ON1’-tifi0G0i.

48727 (RNWG634) TUBULAR FUEL ELEMENT WITH lN-TECiRAL TARGET: PCTR EXPERIMENT. Bennett, R. A.; Nftw-man, D. F.; Vaughn, A. D.; Davenpcmt, L. C.; Robertson, D. E.;Bennett. C. L. (Battelle -Northwest, Rlchland, Wash. PacificNorthwest Lab.]. June 1.1966. Contract AT(45-1)-1830.‘r2p. Dep. C FSTI.

Two tubular fuel elements wJth integrai target lattices havebrcn investigated in the Physical Constants Te6t Reactor (PCTR).Multiplication constants, neutron utilization ratios, fast fissionfactors, and Initlnl conversion ratios have been inferred fromnull reacti~lty experiments snd measurements of spatial distri-hutimm of neutron reaction rntes. Both wet and dry experim$ntawere carried eut In n three-by-three array of lattice cells 37.5”Iong plnced In the cavity of the PCTR. (11 references) (auth)

23

1968

50s15’ COMPAf&N OF CRITICAL EXPERIMENTS WITHCALCULATIONS FOR ORGANIC LATTICES, BUelU, Q.; Grtfotd, ,S.; Martinelli, R.: Orestano, F. V.; Santandrea, E. (CNEN, :Rome), pp 485-92 of Fisicn del Reattore. Romeq Coneigllo ‘Nczionale delle IUcerche, 1968. fhr Italian).

Frotn Conference on Phyttic8 of Reactor6, Milan. See CON F- ,469. ,’

The core for 170SP0 is described; nominsf dimensions are given.Mrihodo for calculating nuclear conaiante and reactivity for or-ganic moderated lattices are described. Reactivity mensttrementaarc mtmmarlacd; measured ind calculated value? are comparedgmphlcaily. (M. L. S.)

ti0814 THEORETICAL ANALYSIS OF CRITICAL MEASURE-MF,NT5 IN A NATuRAL Uft4NIUM METAL-HEAVY WATERLATTICE. Bonalumi, Rlccardo: Zorzoli, Giovanni Battista(CISE, Milan). pp 479-84 of Flsica del Reattcq. Rome, Con-siglio Nazionale deile Ricerche, 1966. (In Italian).

From Conference on Phyalcs of Reactors, Milan. See CONF-469.

A summary deecrlptlon of the ‘physlcaf model used for crUlcrtfiiymeasuremonta in natural U-heavy watet Iaiticett is given. Resultttof ihe experimenin are diecuneed; methode of data anady.vin @reifoe.crIbed. (M. L. S.)

3S631 EXPER1hlENTAL STUDY OF THE NEUTRON CHAR-ACTERISTICS OF FAST CORES [N THE ERMINE THERMAL-FAST CRITICAL A&sEMUI,Y. Bouchard, J. (CEA, Fontenay-nux-Ruses, Frnnre): Vldnl, R. I Mougnfot, J. C. PP 309-25 ofFnst Rcncior Physics, Vol. 1. Vienna, International AtomicEnergy Agency, 1968. (In French). ‘

From Symposium on ‘Fnet Renctor Phytdca and Related SafetyPrubIcms, Knrlsruhe, Germany. 54+ STI/PUB-165(Vol.l);CON F-671 O43-(VO1.1). I

A accilon of fasi-reactor Iattlce wae placed in the ccntrai hole ‘of ihc MINERVE reactor, thus forming a coupled “ihermnl-fasi~”cr!~lcnl assembly. The construcUon of the fi ret core, composed0[ ihe MASL!RCA I-B Inttlcc of 30% enriched uranium diiuied ingraphite, tugethcr wlih the experimental tcchniq~ea uabd is de-arrlbcd. Ntost mcneur.?ments were carried out by the oscillationmethod, using an auiomailc regulating rod, to comptmeaie for rc-actl~ Ity effects. The exprrimcni was conducted with apeclal cazm,OOna io avoid electronic, mtxhanlcnl and neutron perturbatlonaM much as poaeible. The reeulte of measurement of apectraiIndices and of reactivity effects of fiaelle, fertile and structuralrnaieriala are prepcnted, The reeulta of experiments carried outto deiermine heterogeneity effcctn, the Doppler effect of ‘lU andthe Importance funciiona are alao presented. These experimentalvalues are compared with values calculated from treneport theory.(mlihl

37543 MATERIAL BUCKLING MEASUREMENTS IN THEANNA CRITICAL ASSEkf BLY. Bouzyk, J.; Kubowski, ‘J.; La-tek, S. ffnst. of Nuclear Research, Swierk, Poland)., At. Energ.(USSR), 24: 425-9(May 1968). (In Ruseian).

The differential reactivity methed haa been applied to determinqtho material buckling aa well as tbe reflector ❑avi~s io the re-flected, heterogeneous, water-graphite moderated ‘system withenriched uranfum. The meaeurlng techntque and,the reeulta ob-tatncd ●re deBcrlbcd. The reimlta are discussed with rettpect to theapplication of ihc writer height experiment to a complex reqctornyetcm. (tmih)


18471 FUJITHE’R REACTOR PHYSICS STUDIES FOR ST~AMGENERATING HkAVY WATER REACTORS. PART 1. UNIFORMCLUSTER LATTICES CONTAINING U~ OR Pu~/U02 FUEL.B-, A. J.; Jobnstone, 1.; Kemehell, P. B.; Nmvmwcb, D. ~

~(Atomic Energy Establishment, Whafrlth, Eng.). J. Brit. Nuc1.Energy SOC., 7: 61-90 (Js0. 1968). ,,

As part of the study, of 6GHW lattices, a wide range of uniformcluster arraye was siudlsd. BOUIcnricbcd U02 and PuOz/U02

I fuels were uacd, and tho range Included pin diamotern from 0.3 In.to 0.6 in in clustere wblch contained from 3’7 to 90 pins eaob.Mcartttrcmcnt8 of material buckling, detsllcd reaciioo rates andvoid coefficient are compared with tbeoretlcsl predtctiona timingMETHUSELAH U, whfch 1s an improv@ version of tJre flve~rmrpdiffusion theory cd,e, METHUSELAH I, orfgtnaily developed for

,.. . . . . . .SGHW nnnc~nm&t nnd rf~slzn nludlon. nnd fho 6!t-grnup, trannport

~fhcnry redo, WIMS, which hnn nupcrm.d(.~ TIIfJLk. lnuti),,

3085 – (iEEw-R-502) tiEAsUREMENTS OF hfATmlALBUCKLING AND DETAILED REACTION RATES IN A SERfESOF LOW ENRICHMENT V% FUELLED CORES hfODERATED BYLfGHT WATER. Brown, W A. V.; Fox, W. N.; SkIllIngs, D. J.;George, C. F.; Burbolt, G. D. (Aiomlc Energy Establishment,Winfrith iEnglend)). Sept. 1967. 129p. Dep. CFSTI.UK 19s. Od.

Mcaaurementa were rmtdo in the DIMPLE reactor on a numberof reguljw, 3% cnrichcd, U02-llght water Iatticva. fMaUcd reactionrate nwaaurcmcmts wcro made In addition to tbc material buck-ibrga, using moderator to futd volume ratios from 3.16 tu 0.7tJ.One naaenddy waa hcuit.d to LII)”C;[n additwn, the COUI:IIIIJcnsltychaugo on heating to 2St)”C w:ta ti[mulatetf by mpertmg aluminiumvoid plna into the Iatiicw (UK)

42368 EXPERIM~NTS ON NATURAL URANIUM GRAPHITELATTICES BY TN E NULL REACTIVITY METHOD. Casali, F.(CNEN, Bologna); Ghilardottf, Q.; Montagnint, B. J. Nuci. Energy,22: 337-54 (Jone 1966).

The measurement of the Infin[te multiplication factor of naturalurnntum-grnpbite Iaiticee in tbe critical aeeembly R13-1, Boiogna,by the null reactivity method, 1s described. The proccdttre whfchwan nei up for the execution of the measurement and for their tInterpretntllm ia given in detali. The.error on k-- 1 was eatl-matcd to be of the ofder of 2 to 3%, in gdbd experimental condi-tions. “f’he Iatticea had been previously teeted in tbe criiical att-uemhly Marlus. by the subatftutlon method, thus mnklng possiblen direct comparison beiwemt Jbe two meihode. ft appeara thata fair agreement existo between the two oete of reatdta. (auth)

----18577 CRITICALITY OF ARRAYS OF ‘8U SOfi~ON. -Lloyd, R. C. (Battelle Memortal In,et., Rtcbland, Wanh.); ClaY-tc.n, E. D.; ~haimers, J. H. Contract AT(45-1)-1830. Nucl.Appl., 4:. 136-41 fMar. 1966). (BNWL-SA-1078).

The rcsulta of neutron multipUcntion measurements performedwith arraya of ‘Jsll aoluUon apply to criticality safety consldera-Uona In handling soiutions tt a concentration. of IY330 g UII/literend are useful In cbecktng computational metheda. The measure-ments Were made wt th s 17.3 kg ‘3$Uin both reflected and uttre -flectcd arrays. Critfcaf numbere of bottles were determined as afunction of spacing, and the effcci of nddIrtg modcrath!K msieriafbetween the lmUlen comprising ati ●rray wns also examfncd. ?.fontsCnrlrt cnfculniions. wcro found in rcprotiuce the rxpcrlmentai datarrwwmiriy wcli, wlih k,lf being computed to wltfdn abnut 6.03 ofurdiy for thnne cases comp~rcd. (aufh)●

.

.

.

24

.

1968

22832 Llfl,\XItlM AND llRANIUM-PLUTON1 tiM FUELLKD1 tr”~!(”l.:S WITII GRAPHITE AND HEAVY WATER MODERATOR.A (’~)Y P \RISON OF EXPERIMENT WITH PREDICTION. Cogne,F.: M~y~r-l Iclnc, & (CEA, Saclay, France). PP 48-58 of ThePhysics 1’rOMcms in Thermal Reactor Design. London, BritishNucIcnr Energy Snclety, 1967.

From Intcrnntlonnl Crmfcrcrrce on Physics Problems of. Thermalflenctor Dcslgn, London. .See CONF-670607. ,

!hpvrimcntn nn grnphltc -uranium lattices aro compared to theCOfllXRAF code pmdlcllons. The agreement ie eatissfactory over

.-. . . - - . .n wide rnngo of lnttlceR, hut ~ discrepancy rCmtrlnS as far ns thotrmpcrsturc coefficient is rwrwrrmd. Rosulte on uronium-pluto.nium furl r-xl,criments carried Out in ffrc heavy-water and Rraphltafscillttcs Aquilon und C6sar are alSO compnr~ with calculation.(nuth)

33006 1(}:.K’ f Ul{ 1’I!Y31C> miufj~iwrmsOF 1.03 l’l:R(:tA4TEN iUC’HKfJ l’R:\S lUM ME’I’AL, D:O MOJtilL\TKtJ LA’r 1lC 1;S.D“.\rJenrre, Wtiter H. (Pennsylvania State Urdv., UniversityPark): Bflss, Henry E.; Lamung, fhvid D.; Kaplan, Irving; Thomp-amr, Theos J. Xucl. Scl. Hng., 32: 283-91(1968).

Reactor physics parunwtu I’S were nmnsurcd In three hcnvy wa-ter lattices consisting of 0.25d-in. -dmm, 1.03 wt % 2SSUmetal fuelrods m triangulsrstrraya apaccd at 1.25, 1.75, and 2.50 In. Thefollowing quan!ttics were nwusured in each lattice: the rwtio ofeptcadmlum to subcadmlum radintivc ca turea in ‘SEW;the ratio of

!?epicadmlum to aubcndrnium fiasiotm in 2 ‘U; the ratio of radiativecaptures in 2SSUto fissions in 23SU;and the fissions in 2S8Uto fis -Siona jn ~j:u. These ckperinmntal results W’cre used to dculatethe following reactor physics parnmelors for each lattice: theresonance escape probability, the fast fission factor, the multipli-cation factor for an infinite system and the inltinl conversion ratio.Analytical resul(s obta[ned by using TIifiRMOS and GAhI-I are infair agreement with the expcrlmcnlal rcsulta. 111 refcrcnccs.(aulh)

35s93 (EURAEC-1882) RESULTATS D’EXPEllliiNCESSOUS-CRJTIQUES NEALISEES SUR DES RESAUX Rlo-(lq EN-RICIiIS A 5 I)El{ CENT. (Results of Subcrltlcul Exl,crinients ,Carried Out on 5 Percent fjnriched ~20-UC+ LutllcctI). Debrue,J.; hIewissen, L.; hlotte, F. (Centre d’fitudt? de l’Energt6 Nu-cleaire, Brusaeis (Belglum)); BasseUer, J.; Delrue, il.; .Fo8eoul,E.; Haubert, N.; Lsmotte, H.; Stievenart, M.; Van Deyck, D.(Saciete Jselge pour l’IndustrlF Nuclealre, B~usaele). July 17,1967. 199p. (in French). {EUR-3378), Dep. CFSTI.

.Work performed under United States–Euratom Joint Researchand 13evelupment Program.

The resuJtrn of all the different typca of mcnsurements car~ied ,out on rnul~rilicat afl~emtdies u~ing U02 with a 5% 2SSUenrichmentin the ‘f’liLliS reactor at tile Cenlsw d’Etudo do l’Energie Nu-,cl~tilre (CENj at hlul aro preacntcd. The Iatticos atudled wore ofthe .bquare plti-h type and tl,e li2fJ/U02 ~,atlo hod auccesrnively the

five following values: 1.51, 2.63, 4.13, 6.33 and 9,36. The maximumnumtwr of fuel elements availabie wes 500, these bavhrg a usefullength of 376.5 mm and ‘ISuseful diameter of 7.8 mm. The claddingis ~IU4 (301) wilh a Ihi( kness of 0.2 mm. The followinlt m~”aburinJft~hntqucs were used: the Invvrso Multlpllcatlon Tuchnlquo (lhl T),tbe Source Ejoctlon Tccluriquo (SST) and the i’ultrod NeutronsTc~tti!lque ( i~NT). A certain number c)f Mtiat4UrtiInc!lt result~ were9cJet [MI in order m Interprcl the varinllon in thti ctmructtirlrnticsof the u>t.cmblieii IIa a functiun uf n doterntiuud Vnriubie (ch~rging,“buckling;’ potsontng, etc.). (nuth)


Lattices35594 (EURAEC-1882(Annex)) RESULTATS D’EXPEftI-IINCES SO,US-CRITIQUES REALISEES SUR PkS RESAUX H20-U%EN RJCHIS A 5 PERCENT. (Reeults of Subc.$itlcal ExperlmonteCarried Out on 5 Percent ~nrlched H20-U ~ Lattices) ., JJcbs-ue,J.; Jfewiasen, L.; hIotte, F. (Centre d’Etu e de l’f?nergle Nu-cleaire, Bruseela (i3elgtum)); Basaelier, J.; Delrue, H.; Fossoul,E.; Nauhert, N.; Lumotte, H.; Stlevermrt, M.; Vnn Deyck, D.(Soctete Beige pour l’Industrie Nucleaire, J3rusaels). 1967. ,133P. (In French). (EUIi-3378(Armex)). Dep. CFSTI.

Work Wrformed tinder United States–Eurntom Joint Re6earcband Development Program.

Results of physics measurements carried out on subcriticalaaaembliea usihg tJO with a 5% ‘% enrichment Jn tbo TIII?TIS

kreacto~are glvcn. T c lattices studied were of the squnrcpitch type arrd fhe H20/U02 ratio hnd euccessivcly the fivo follow-ing values: 1.51, 2.63, 4,13, 6.33, and 9.35. The maximum numberof fuel elements availsble was 500, these having n useful length of376.5 mm and a useful diameter of 7.6 mm, The cladding 1s steel(304) with a thtcJmeaa of 0.2 mm. The following measuring tcwh-niquea were used: the inverse Muttlplication Technique (i.kf’r), theSnurce’Ejection Technique (SET), @d the Puiscd Ncwtrone Tech-nique (PNT), (D. C. C.)

6121 ANA LYSfS OF FTR CONTROL-ROD EXPilRiMENTSPERFORMED IN ZPR-3 ASSEMBLY 48 AND 48A. Eqgstrom,S. L.; Br2Mt?tt, R. A. fBatteile-Paciftc Northwest Lab., Rich-tand, Wash.). Trsne. Amer. Nucl. Sot., 10: 528-9 ff40v. 1967).

From 15th Conference on Remote Systems Technology andAtom Fatr, Chicago, D1., Nov. 5-9, 1967. See CONF-671102.

33061 MEASURED CRITICAL SPACINGS OF PLUTONIUMARRAYS. PART Ii. Finn, H. F.; Pierce; G. A. (UtrIv. ofCalifornia, Livermor6). Tran9. Arden. NUCL Sot., 11: 379-80(Jrme 1968).

From 14th Annual Meeting of the Am&lcan Nuclear Soclcty,Toronto. See CONF-,68W301.

25086 (IEA-139) PROGRESSIVE SUBSTITUTION EXPERI-MENTS iN U~ LATTiCES MODERATED BY D2-H20 MIXTURES.Fronzen, H. R. (instituto de Energla Atomica, Sao Paulo (Bra-zil)). Apr. 1967. 30p. Dep.

Bucklin ‘ mcnsurcmenta for cores of uranium oxide (3.00% en-?rlched In %) In different mixtures of D20/~f20 were pcrfOrmed

In the NORA reactor by meane of a progressive substitution lech-niquc. In order to check, the rcsulta, come experiment were aleo’carried out by the suhstflution technique in critical htttices forwhich the bltcklin~ was rslrendy known, 8nme aubcrltical expcri-mcntn were aluo pcrformmf to give ndrfitlorml information rihoutthe truckllng ohtsinml by substitution experiments. The analysieMan done by three regione, two group theory and a correction waeIntroduced in omfer to hrkc into nccounl the effect of the m?ffcctor.For n D20 conctmtrntlon of ‘39.50% anrf n lattice pitch of 6.544 cm,the material buckling with void was obtnined by three rcgirrns, onegroup !hcory. All the results were found to agree ss.tlsfactorllywith the rcaultn from crttlcal exoerimrnts. (auth)

33046 EXPERIMENTAL BUCKLINGS OF SiMULATEDBURKED-UP NATURAL URANIUM CLUSTERS IN HEAVYWATER MODERATOR. French, P; M.; Solheim, R. (AtomicEnergy of Canada, Ltd., Chalk River, Ont.). Tram. Amer.Nuci. Sec., 11: 251-2 (June 1968).

From 14th Annual Meeting bf the American Nuclear Society.Toronto. Sec CON F-680601.

25

Critical Experiments:196832999 EXPERIMENTAL MEASUREMENT OF K.ANDVfN

SUflCRITICAL LATTICES. Barrington, J.; Lanning, D. D.;Thompson, T. J.; Kaplan, L (Massachusetts, fnst. of T~h., Cam-bridge). Trans. Amer. Nucl. fbc., 11: 48(June 1968).

From 14th AnnuaI Meeting of the American Nuclear ticiety,Toronto. Sce CONF-680801.. ‘

22098 ‘ MEA9URkME@$T OF MATf%’RIALBUCKf,jNGANDDIFFUSION COEFFICIENT IN HEAW WATd3R MODERATEDI,\rTICES CONTAINING NATtll{ALUt% FUEL CLUSTESfS..

‘}{ocr, \V. (Eldgrnoeselsched Ifmt{tut fucrltenktorforschung,\VuercnllnWn, S!\ltzerlnnd): Lutz, N. R.; Richmond, R.; Perseoo,R. pp 111-160f The Physics Problems ln Thermal RcnctorDesIgn. Lendon, Brltiah Nuclenr Energy .wiety, 1967.

From lnternntlmmlCo nfrrefrceon I’hyslce Problems of ThermtfiRrsctor WSISI’I. London. See CONF-670607.

A dcw’rlptlnn IS t?lvrn of a series of cxfrcrlmcnts cnrrlcd out In .rwl~port of SN1ss rcnctor assessment .studlcn nn heavy water mnd -erstwf htticcs contalrdn~ nntural U02 cluster fuel clvmr. nts. Therxpcrtmmrts, u hlrh involved mmsurcmcnts of material hucktlngand diffusion cncfftcicnts, wrro dcslgncrf to givo a compailaon oftho result* of m,’asurcmcnts on Rlnglc-zone lattices, in tho SwissWI,, rttiral asccmldy MINOR with thnsc gtwm by suhstltutlon mea-suienwnts in the SUcdlsh rvactor 1{0. A compnrlrron of the twoLWtSd w~rlnr(~nt~l rf~I~cOnfirmrd hat nccurstO results can be .-ektaincd b) the substitution method u~ing very small numbers offurl clusters, but ahoucd that, in sorqo caacs, the mcthcd may beMcmlicantly in error, and emphasized the nb~rf to Invcfitlgato thecnndjlions in u hich these errors may occur. The results Of theburkllng measurements ~~cre iomparcd with the predictions of the,UK4HA ●swwsmcnt cede METHUSELA!I and Urc Swedish cedoIWUI:S. Roth cmfcs were shown to @ve satisfactory results overlb~ rsngc of lattices cxamfned. The mcmsumd coefficients wererrrll pred!ctcd by Urc theory of i3cnolst. (nuth)

12032 (NAA-SR-Mem*12472) NUCLEAR SAFET”Y SRECORE 111FUEL ELEMENT STORAGE. Ketzlach, Nqrman(Atomlcrf Intermt!orud, Canoga Pprk, CalIf.). May 17, 1967. “7p. Dep. C FSTL

The nuclear safety of a ilngle-plane array of SRE Core 111fuelelcmente, spaced on 12-inch centers, has been evaluated. Thearray Ia Ieso than 45% of crltlcal, based on the mans/urdt areaprinciple for the fuel rod sizes of interest. This is independent

“of the degree of wa~r floeding. A fully-flooded array of the a6-aembl y of elements spaced aa stated ahove wouId have a k ~if ofIeaa than 0.6. An unfederated aasembly of fuel of the given en-richment having a [email protected] equivalent to water would .require at Ieaet three times as ‘much fuel for crltlcality, Indepen-dent of spacing between elem,ents or the ,thlckneea of water re-tlrctor. (auth) . . .

.

5746 TEhf PERATURE COEFFICIENT OF ,IW~-UC+-H20LATTICES. Kobsyasht, S. (Hltacht, Ltd., Tokyo): Uotinen, !V. O. Tr’ans. Amer. Nucl. Sot., 10: S64-5 fNov. 1967).

From lSth Conference on Remote Systems Technology andAtom Fair, ChIcagn, Itl.,” Nm. S-9, 19670 See CONF-671itJ20

Lattices1865 (JPRS-42322, flp 102-57) CRITICALITY Of-’SYSTEMSOF INTERACTING SUBCRITICAL ASSEMBLIES OF FISSIONABLEMATERIALS. Translated from pp 189-201 of Krltlchefdde Pa-rametry Sletem a Delyaahchl mleya Veshchestavami 1 YadernayaBeaopaanoat”.

Scml-cmplrlcal methods for cwfllunthrg tho nuclear tmfcty of asystem of hrt~”ractlng mdxxltlcsl aerncmtilmf aro cxnmlncd. Thomethods dlticuwwd urc: (1) tlw equfvnlrnt fflmwrnlunti nwthod,(2) the mcthud of the #aft Bond wrglc, (:1) the interaction param-

1 eter method, nn~ (4) tho hemogfmlzatlon methud. A rmmmnry ufpubllahed experimental data 1s also preaentcd. (H. D.R.)

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?3755i MEASURfihl ENTS OF FAST F1SS1ON RATIO lN NAT-URJiL URANIUM CAHBIDE HEAVY WATER LATTIC~:S. Ma-racci, G.; Rusrttchelll, F. (CCR-EURATOM, Ispra, Italy). Energ.Nucl. (Milan), 15: 330-4(May 1968). ,

The meaauremente of the faat fiaaion ratio performed at theECO reactor in natural uranltun carbide heavy water Inttlces, by

“Urtt integral gamma counting technique, are presented. The reaulfsof the meaaurementa carried out on Urrce different types of ele -ment6 are compared with Ureoretfcal values calculated by thePINOCCNIO code: the agreement found Is saflsfactory In all thecaseo ,tnVoatlgatcd. (auUs)

16288- (Nki-TN:~2iO) ANALYSIS OF CRAISYL FLUO-RIDE SOL~TION REACTONS CONTAINING VOIDED TUBES.Mayo, Wendell (National Aeronsutlcs and Space Admi~~tratlon,Clevelsnd, Ohfo. Lmvlrf Research Center). Feb. 1968. 24p.CFSTI.

Critical experiments with sidly enriched (93.2% ‘SSU)urmrylfluoride -water solution rcactora thst contain arrays of large-diametcr void tubca w’crc analyzed satisfactorlty. A calculatlonafmethod that involves the dlrcct application of wIdt,ly usrd multi-group computer pmgrnms and tcchnlquct! to cases of extremeheterogeneous voids JS evaluated. Experimental crltlcrd solutionheights for COI’CSthat contain no void tubes and for 19.31. and ,37 void tubes with a 7.6 S8-cm diamclcr were obtahrcd by usingthe NASA ZcrO Power Reactor-II facility. Both unrcfl~”cted corca

‘ and cores radially rcftcctcd with 1S.24 cm of water were consld -ercd. The void arrays with trinrgular Intlice pitcht, s of clthcr9.652 or 10.922 cm were ccntrrdly Iocntcd In the 76 2-cm-dlnmctercore tank. The critlcni heights of the voided rractors rxng(,d from21 to about 84 cm. The catcrdational method consists of firstcomputing axial Icakage rates from xxiatly finite ryllndrical CCIISthat contahr the void tuhc and a proportional amount of (uel solutlofs

. The CC1lttlmcnslona and furl arc obtained from the correspondingcritical rcnctora. Two-dimensional (r-z) S4pl tran~port calcula-tions with flvc energy groups of finite hclgh! cyllndrlcnl rrlls areuncrf. Thr axial It,akngv rntcs pt. r rmurcc nwtmn, ,A,ts in, II frvmthe crll cnlculnllrme, mr Inrnrlx)ratrd Into tmf,+li!slc n-lunal ra -dlall} Rnltc rwactur cnlculollfm=. h} d, llnln~ an ail,t( It”akngtt C!VSSnt-c!lnn for rnrh mwrgy Krrwp to ~11,,UIBII,, r .III ii IN-U!r,m strr,lm -Ing nut of Ihr voldrd !’uRlon d thr I(,nr!or Ihs t!knnl IX{,I trlnrn.which nrc nIso obtnltrrd f! on) tlw tun dlmmwlwrnl CC.11- SIX.Impnrtant cnpvclnlly for thr frly>ltcr Ilttchl I I nclt~!s thrd contnlnthe more conccnt rnt vd fur-l nolut ions 1“110c~lcul!rll~m~l ml!h,xtis uatlsfactory for thr rwrctnrn mamlnvd arvt IS I r.-IriIlv .mlnplvdfor uao with olhrr reactor confl~utnfkww pwwldtd that Iso -dimenaionat (r-z) celts can bc dcfhrcd npproprlnlcly (nulh)

tlo3 2$$&~ sEED-~~NKET CRITICAL LX PEilMltNTS.Mltant, S. fRettls Atomic Ibwcr lab., West Mlfftln. Pa.). Trana.Amer. .Nur-l. .soc., 10: SqS (Nos. 1967).

prom 15th C,mfcrrnrc on Remote Syatcms Technology andAtnm Fair, Chicago, 111., NnT. 5-9, lq67. *P t’! INF-~7111_12.

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1968

“14161 (wArD-TM+i14) SMALL ZJW i-tJEL$;D SEED-AND-nLANKET CRITICAL EXPERIMENTS. Mllnni, S.:\l’etss, S. H. (Rettla Atomic Power I,nb., Pittsburgh, Pa.).fiov. 1967. Centrnct AT(11 -1)-Gen-14. 167p. Dep.CFST1.

A scr{ug of f,l~hl small m.~,rf-and- l)lnnkct ~rlt[cal aSS~mI)lIe~nrrc stud!cd al [he Rctt is Atomic Powt,r Laboratory. Rod-’typeRoodfuel t,lcmcnts which conta Incd either 23~Uor 2]SUwere uti-Ilrrd so th:it a dlrt,ct compn riwm could he nmrfe hctwccn the lat-tlcc rharndtcrlstics of the two furls. Alr+o, hlankct rc~ions whichmnlalned rod typo elements with’elthor nntural ThOt or 1 w/o“V: (l:.- Thoz were con>par,,(i The OIKII!ns.wmbllcs were of twoPI IIIClPnlIYPC; Thr first type wn, n I rrlatv:ulnr array having arrn!rnl sm-rf rrEinn surrmuwkvl by a wet I]lankct with a mctal-to-!mlcr ra![n nf n!,m.d one, and ~he flccond wns a hrxa~onal array ‘hnving n cent r~l seed region rwrrnrtndc(l by a t lghlly packed dry ‘Idarikv( with a mr.lnl-to-watrr rnllo of obmd 9,2, All cxperlmcntsM th,. ~,. olj!hl n..f.mltll,,.~ WOI,. rnn,luvl,.tt al 70”[” Il>mprr’.llurc,1. q,!,lftl, w IWI,<d Ihc wot l,l:!!,k(, t nvw. mlIllI.sI w-t ISctudllvl In thelllxh 1/ ,,,,.$, ,1,,,,, I’r.ql [.’nr[l It~ nt JNll~f.’n,,tl fifiil ,,qI (nuth)

22844 INTKRPRETATION OF CRfTICAL EXPERIMENTSWfTH URANIUM-PLUTONIUM FULL ELEMENTS. Naudet, R.(Centre d’hturics Nuclealres, Saclay, France). pp 109-25 ofFurl Rum-up Prcdlctlons In Thermal Reactors, Vienna, inter-national Atomic Energy Agcncyo 1968. (In French),

From IAEA Meeting op Fuel Rurnup Prcdlctlons in ThermalRcactorq, \’lenna, Austria. SCe sTI/PUn-172; CONF-tj70411Jo

A sot nf criticnl cxperimrmls pcrformcrf Rucccssivciy {n thehcnvy-wntcr pih? AQIULON U and the grnphite pllc CESAR wandcsi~nml 10 compare the ncutrmr propcrtlcn nf the two Iatllces,which nrc gcwmt.trlcally Identical hut in whlcb Ihc fuel compofli-tlnn is sli~htly different. The same fuel elnmcnts were used inthe two pllms. I.r.. uranium mclai rods of uniform rfiamcter. Thefnllowl”~ rnm{,nsi[{n~s ux-rc compared: Control set: naturalurnnium; Scl used as an intcrcompnrison standard: urmium veryslightly dcplctcrf or enriched in ‘SU (0.69% -0.83%–0.86’%); Threesctn to h{, s[udiorf containing plutonium: 1P: natwrai uranium +0.04’~ plutonium: 2P: highly depleted uranium + 0.30% plutonium;3P: sim ilnr to tP but with plutonium containing q higher propor-tion of the isotope ?(OPU. In AQUILON the experiments were per-formed over n whole series of lattice spacings so as to vary tbespcctmm over a wide range, but all tho mcnsurcmcnts, with onecxccpti,m, were made at environmental temperature. In CESAR,the cxpcrimvnts involved oniy one or two spacings, but a widernngc of Icmpcrature. Up’to the present time measurements havebeen made at 20, 100 and ZOO-C, and they wii} be continued at 300and 400”C. The purpofie of these experiment.s is to obtsfn data onwhich to evaluate the equivalence behveen ‘SU and plutonium inconditions similar to those encountered in natural uranium reac-tors during irradiation, and to test the calculation methods. Theexperiments performed in AQUILON are described in greater de-tail, but the results already obtained in CESAR sre slso indicatedby /WIIyof comparison. (auth)

18545 (RNU’L-fi22) PCTR MEASUREMENT OF km FOR~ll{ANI[l\f l,lT[l[(lhl sll Pf;I{C~[,L, Ncwma”. ID. F. (Bnttr]}O -Nor!hwest. Itichlnnd, Wnfih Pncific Northwest I,ab. ). Dec. 20,i!167 Cnntrnct AT(4s-1)-Isno. 70p. DCp. CFSTI.

}.XIIIrimuntnl vnlucfl for infinite mrdium neutron mulliplicntlonfnctor. k~, hn~c hcrm drterminrd for n grnphltc mnderutrxl suprr-c-cll utill?in~ 2 l’~ wrrlchwf U fuel nnd 2.93 wt % L1-in-Ai tnrgetI“ srl,nrntc prnccsn tuhcs. In n thrtm-to-onc rntlo. Dctormination.sof k- wrrc mndr with !hc coolant chnnncls wet nnd dry to obtainnn rstlmatr of lhc rcoctivlty cocfficionta duc to wntcr Ions. Dotbn 6 . 6 nmi 5 . 5 array of test CCIIS were hmcrtcd in the PCTRlost cnvily for thrsc mcnaurcmcnta. Rraulte of cxperimcntaimensu rcnwnts nrv listrd. (nuth)


Latticesd7890 (AEcL-2778) IjATTICE MEASUREhfEf4TS WfTH i9-ELEMENT RODS 01: ThO#SU~ IN HEAVY WATER MODERA-TOR. PART f. f3UCKLING, FfNE STRUCTURE, AND NEUTRONSPECTRUhl PARAMETERS. Okazaki, A.; Durrani, S. A. ‘(Atomic Energy of Cnnnda Ltd., Chalk River (Ontario)). Oct. ‘1967. 47P. Dep. CFSTI. CAN $1.50.

Latt’icc pn ramctcrs were mc~surcd for hcntT-wnter-mcderatettlatliccs of 19-clcmcnt clwtcrs of ThC+ containing 1.5 wt ‘%en-riched UOt [93 st. 7, 21SU). Iiucklin~s were ddcrminod fromr.ri[lcnl suhaUh!tlon mcnaurt. montm In the ZED-2 reactor usingh!l(”It I;TL. n two-~ ro!!p hctrrngrnom!s rrnctnr rIwk,. Neutronck.mitv dl~{trlh!ttltmc nml Wcstrott epr. ctrum p~r~mrtrrn r andT N,.n-. cdflniwvi fu)m mf.n6utrcri ‘Rrdn. ‘fM!II, nml l;l I,II nctlt itksIn f!Iil Ik$tt., torq. hlonaurcmrnls ucrr !UIICICfIII 1+(), nlr, !120

Inn,] 1111-4nfmilnnta nmf for 22, ?4, 2W. nnd “l> Vm trl:lnmtl~r, inlticr plt(”hcs. (nuthl

‘22836 CifALK RIVER STUDIES OF QO MODERATED NAT-, URAL URANIUM AND 23SU-THORIUM LATTICES. Okazaki, A.:

Tow!res, B. M.; Durrani, S. A. (Atomic Energy of Canada Ltd.,Ontsrio). pp 95-102 of THe ,Pbysics Problems in Thermal Re-actor Design. London, British Nuclear Energy Seciety, 1967.

From International Conference on Physics Problems of ThermafReactor Design, London. See CONF-670607., Progress ia dcscribcd on an investigation into the adequacy ofthe four-factor two-group description of the neutron cycle, bycomparison with experimental measurements. Maximum use isrnadc of cxpcrimcntal information,, but some theory and basic nu- .kiesr data are involved. The cniculated ~ff values show system-atic trends with pitch and type of fuel bluster, and with coolant.Explanations for these trends are being sought. In addition, iat-tice paramcker measurements on D20-moderated lattices of 19-clcmcnt rods’ of Th02 containing 1.5 wt. % 2JSU02 are reported.The rneasurcments were made for four coolants over a range oflnttim. plfrhcs. kmth) ‘

U882 (AEC L-7J779) LATTICE MEASUREMENTS WfTHlg-E[,FhfENT Kc?DS UF Th~~~5U ~ IN HEAVY WAT’ER MOD- ‘ERATC>R. PART 11. RELATIVE FISSION RATES, FAST FISSIONRATIO, CONVERSION RATIO, AND COMPARISON WITH CA LCU-L.4TIONS. Okazski, Albert (Atorrdc Energy of Canada Ltd.,Chalk River (Ontario)). June 1968. 41P. Dep. CFSTI. CAf4 ‘$1.50.

[.alt Ice parameter measurement ‘of heavy water mederstedlattices of 19-element clusters of Th ~ congi”ing 1.5 w/o U02(93 a o ‘~61!)arc presented. Relative 2311, 2 U and 2S9PUfissionrates, fast fission ratio, and conversion ratio mcaeurements aredc.scribed. D20, sir, H20 and organic HB40 coolants were studiedat 22 and 2a CM t rianqular lattice pitches. Additional anaiyscs ofthe critical Substitution meusurcrqcnts have been made and re-vised bucklings are glvcn. Calculations made with the LATREPand HAMMER codes are compared with measured lattice param-eter. Both codes underestimate the buckling by up to 1 m-z withthe largest discrepiincy at the tightest lattice pitch. The calcula-tions ovcre.stimate the neutron disadvantage factor and conversionratio. (auth)

“33026 l! UCKi.iNG AND PARAMETER ME.+SU1{LMENTS iNTlf K Th-lljO OIKi,\NIC SYSTEM. Pellnrin, D. J.; Ruummm,,N. i’.: Sutt~,rffui J,1{. M.; Vuraiervclde, V. D. (E, i. dui’ont deN~I:WtUW UMJCCJ., .Aikcn, s. C:). Trans. Amer. Nuci. suc’., Ii:2Xt-.f(June lYfi8).

i rum -ttitAnnuai hleetieg of the American Nuclear society.T[]routu / See CON F-6 W)601. J t

27

1968

33060 MEASURED Cf@CAL SPACiNGS OF PLUTONIUMARRAYS. PART I. Pierce, G. A.: Morton III, J. R. Wiv. OfCaltfomIa, LIvermore). Trsns’. Amer. Nuc1. Soo., 11: 3’78-9,(June 1968).

From ,14th Annual Meeting of the American Nuclear Snciety,Toronto,. See CONF-680601. ,,

63432 A “fiEWfW OF THE ‘ExPERIMENTAL AND ANALYTI-CAIi RESULTS O(F THE HIGH-CONVERSION C,RfTICAL EXPERI-MENT. Plumlee, Karl E.; Pennftrgton, Edwtn M. Reactor Fuel-Process. TechnoL, 11: 117-20 (Summer 1968).

Criticality calcutatiorts and experiments for enriched U02-fuclod water-moderated core are preaepted. The fuel elemcntaconelet of Tyw 304 atntnleee eteel- and AJ-clsd pellet-shapedU02., Calculations fnr vnrloue geometry BORAX-6 and Hi-Cco,roa are preaent~. (D. C, C.)

63433 REVXEW OF RESULTS ok THE ixkfPGE CRITICALEXPERIMEN’7. Pluml+e, Kari E. Reactor Fuel-Process.Techr@., 11: 121-2 (Summer 1968).

Phyalca meaaurementa for four different Sores In the DIMPLEcritical aasernbty are presented. The cores conalst of HI-C@net-type enriched UOt fuel elements with Type 304 stslnfeeeetcel and aluminum ,@lsddlng. The aseembllea are water-render- .

‘ ated. (fY.C. C.) . .

6377 CRITICALITY OF HkTEfbGENEOUS ARRAYSt-lN[)~RGf)ING DI~(_)I,lJTI(lN. ff{ch~y, c. R. (u~~t~ll~ MemorlttlInst., Illchlanrf, Wash.). Nuc1. .SCI. i?ng.. 31: 40-6(19 Gil).

Lip(,rimcntal dnla to CSUIIJUSII’crillcnlitv control specificationsfor rnrlrhcd ur:tulum rmls undorj:~,lng dissolution arc extremelyIinlifcd. A princi[ml difficulty In trenting Um prublcm theoreticallyIS Ih:tl the rcaon.anr!c ahso!’bing.za%l IS ,admlxc{] in the aqueous SC.-lullon In n hlch the roda arc lmmcrscd. The “narrow rcsonsnce” aand “lnflnllc mass’) WIrrOxlnlntlOns arc api)llcd; nnd from this ap-pllmttioh, cxprcssibns arc developed for treating rceonance captureby an nbsorbing Iump cmhdded {n a mnderator ndmLxcd with theabsorber. The computed change In tlw crlticitl buckling of a hctcr-OIWncOus array on rwlaclw the wa~r moderatnr by a uranyl ni -trntc solution ia In good a~ccmcnt with eq)crimcnt. Results fromsurvey calculntlons [or 3 ,and 5 wt % 23SUrods kattlced in uranium-watcr mixtures arc g-ivc,n. It was concluded that for cnric

Wc”tsup tn 5 wt ‘~ ‘S$if, rflssnlvcr vosaele dcslgncd geometrically safe forwaler-mcdcrated arrays bf uranium rode wili remain safe during ,

“ the rtlssolution process. (auth)

blos ANALYSES OF ffftOfJKNAVEN 112UJ%% OXfDE,LfGftT- AND HEAVY-WATER-MODERATED LATTICE EX~EfU-

MLNTL &hgal, Sal flaj (f3rookheven Natloul lab., UF@OC,N. Y,). Trana. Amer. Nuci. SnO., lot 506-7 tNuv. 1967).

Nrum 16UI Cmftmence on Remote SY~tema TeC~OloID adAtom ?’air, Chicago, In., ~~,. ‘g, 19670 *6 coNF-6711020 .-.


Lattices

1875 ‘“ AN EXPERiMENTAL COMPARISON OF THE FASTAMI THERhlAL NEUTRON BUCKLINGS IN A URANfUM DIOXIDELfGHT-WATER MODERATED CR{TICAL ASSEMBLY. Shaw,Robert Alexander. Ithaca, N. Y., Cornell Univ., 1967. 64p.

Thesie.A comparison of the spatially deperstent faat and thermal neu-

tron flux profilce has been made in the Corncil Unlvcreity ZeroPow cr Hcactrrr, a light-water mmlcmtcd and rcficctcd, 2.{% cn-richcd, U02 fueled, alumlnum ciad, triangular pitched critical .assembly, using the core which has a nomlrral water-to-fuel ratioof {.5: 1. The radial buckllng, defined by u Ica.vt-aquarea fit of~hc radial fiux profile to a JO Bessel function, is chosen ae ● con-.venlent single-parameter characterization n[ the profllc for com-parison of flux profiica. The radiai faat flux profile was deter-mined by ualng a acmiconductor detector to detect flaaion fragmentafrom the fact fiaaimdng of Th-232. The radial thermal flux waa

“dcte_rmlncd by thr’ Irradiation of mnn~ancke fo~~~.-T~c I,ucklinrfearc fnund ne a function of the radial dintancc (r) from the coreccntvr by pvrform]ng the least-squares flt on data tnkrn frnmthv core ccntvr out to r. The thcrmai neutron reflector humpcmIscs the thcnmal flus to deviate slgnlflcantly from the J- dc -fwndcncc for r greater than about two-thirds of thv corv radlua.C?maldcr[ng the rvgion in which the thermal fiux gcwraliy foiiowaa & dcpcnckmcr, the ratio of the thcrmai buckling to th(, fxht lwck-Iing is found to bc 1.13{ * .052 and 1.07fi * .052 for the two largcatvaluce of r in thie rcginn for which the huckllnga aro calcvlatcd.An mralyela nf theoretical fast nnd thermal flux pmfilca for thlacore which were calculated indcpendcntiy of thin work supfwrtathe conclusion that the ratio of the thermal huckllng tn ttw fastbuckling is greater than one. Ilowcver, a prcciec compsriaon lanot valid hccauee the fast flux waa thcnrdfcally calculated forneutrons in the energy range between 0.821 MeV and 10.0 McV - “whereas thr effective fission threshold for Th-232, used to ex -pcrimcntaliy dctermlne the fast flux, {a afmut i .35 hfcV. (D!aaer.Ab.vtr.)

6115 CRITICAL EXPERIMENTS WiTH PHOENIX Ff.’EL IxAN MTR MOCKUP. Smith; R. I.: Davia, E. C. Jr.: Wlllimns,

. L. D. (Batt.b~e-I%cIfto Northwest Lab., Ricfdsnd, Wash.).Trane. Amer. Nucl. Sot., 10: S37 (Nov. 1967).

From 15th conference on ~emote Systerna Technology andAtom Fair, Chfcagu, ill., Nov. 5-9, 1967. see CONF-671102.

33047 BUCKLING MEASUREMENTS IN A HEAVY-WATERSUPERIATTICE. Tanner, (L J.: Andrewa, D. G. (Univ. ofToronto). Trane. Amer. NUCL Sot., 11: 252-3 (Juoe 1968).

From 14th Annual Meeting of the American Nuclear Society,Toronto. See CONF-680641.

1565 (ORNL-CDC-t) EFFECT OF UNIT SHAPE ON THECRITICALITY OF ARRAYS. Thomaa, J. T. (Oak RidFe Na-tional Lab., Teen.). Oct. 1967. Contract W-7405 -eng-26. 19P.Dep. CFSTI,

The known criticality of ur@um metal em~iched to 93 v % in2SCUaa au~r{t{cal cylindrical components inunreflwwdarraY4is used to exploro component geometry effects in such arrays.Three bsaic geometries pre chosen; the cube, the sphere, andthe cylinder with equal height and diameter. It ia ahown that the,muit ipiicatlop factor 0[ a u’nit defines sizes of the three shapeausefui in establishing critical armya equivalent to a givenreference array. The number of con~nenta and the averageuranium density of the oqulvaient arrmys are the same aa tbereference array. , The effects of chnngca in averuge unanumtdensity and component tnasa oh the array muitipiicntion f~cturarc lnve~tlgutcd. (mth). .

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32976 (nflT-2344-12) ilEAvy WATER LATTICE pROJECTFfNAL RI? PORT. Thompson, T. J.: Kaplnn, I.; r)riscoll, M. J.(ecfs.) {Ml!ssachusetts hat. of Tec$., Cambridge. Dept. ‘of Nu-Clear Engineering), Sept. 30, 1967. Contract AT(30-1)-2344. ,208p. (MITNE-FJ6). Dep. c FEiTI.

CRITICALITY STUDIES — physics of heavy wrltcr-m’oderated ‘sllghtIy cnrlched uranium-fueled lnttlccs, (E/T)

NEUTRONS —buckling In heavy water-moderated uraniumoxide (U~)-fueled lattices, (E/T); multiplication constantmcasurcmcnts in heavy writer-moderated urantum oxide(UOJ -fueled lattices, fE/Tl

URANIUM-235 —neutron fieelon ratlb to hranlum-238, mea-surement by y epectromctry

S0788 (AE+30) STUDIES OF TI{E EFFECT OF HEAVYWATER IN THE FAST REACTOR FRO. Tiren, L. 1.; Haekaneaon,R.: Karmhng, B. (Aktlebolaget Atomenergt, Stockholm (Sweden)).Aug. 1968. 25p. Dep.

Core 9 of the FRO’ fast critical aeecmhly wae diluted withheavy u’atcr to 24 vol. per cent, contained in thinwallcd Cu cans.Measurements of the criticai masd and the reactivity coefficientof heavy w’atcr In thla core are presented. The effect of theheterogeneous core composltimr on these Items Is also discusacd.The results nre compared with theoretical predictions ueirrg sev-eral computer codes. Criticality Is.accurately predlctcd, but themeasured rcnctlvity coefficient of heavy water ia about 20% Iowcrthan the value frbtaincd with the best available methods, involvingthe SPENG and DTF-4 progrrrmmes. The result of bunching mea-mremente, in which the degree of hctcrogenclty of core compos!-tlon Nas changed, ia compared with theoretical eatlmatcs of theresonance shielding, flux advantage nnd lenknge components ofthe hMerowmcitv effect. (auth)

44885 INNWL-692)” PCTIi MEASUREMENT OF J& FOiiI~I{ANjI,3T IIIS3RJTH sUPERCELL. Vattghn, A, D. (Battelle-Northji est. Rlrh IwvJ, W’ash. Pacific Northwc!!t Lab.). Feb. 1,1968. (’ftntrfi, t Al (4S-1)-1830. 48p. Dep. CF,$TI.

A measurement ts made of the ncutrordc paramctere for almv nhsorptlrrn target In n supcrcclI conalstlhg of a thrce-to-tu n fw.1-h-fsrget ratio with separate tubes of uranium fuelnnd bismuth metal target. Each tube le water cooled and cur-rountlmi I)y a graphite moderator on an 8,0” lattlcc pttch. Tbehlnmuth tary,ct clcmcn~ are relatively targer (3.750” O. D,)than the urnnlum fuel elements (1.508” O. D.) tn order to lrra-dtatc an much of tire target matertal aa poeetble because of the●lgrdflcantly low blemuth cross sectton. F@r tncb equare hole

bnr~ nrc rcmovrd frnm each tnr~rt ~eli ‘tc contnln n r~und nlu’-mlnum lwo(.t,~s f!dw with the tnrgct r!lcmonts. The grnphltf. hoIehnr~ for the fuel (elk cmrtnlncd 2.0” O.~. h(>lcR and 71rr!(1nlumprm.css tulws. f’l!c cxpcrimrnt Is conductwf In the Phyfli,. alCons lnnts Testing Rrmrtor (PCTR) for n zero cxprmurc! GWC atronm tcmpcratvrc. The rcactlvlty effect of cooiant Inss In ln -cludcrl In ttw,sc mcneurcrnents. (auth)


608fKt (BN\VL-702) PCTR MEASUREMENT OF k- FORURANIUM TNORtA SUPFRCE1,L., Vaughn, A. D.: Flclsch-mnn, R. M, fl~ttf.llc-Nntthweet, Richland, Wanh, f%ctfic Norih-Wf.st IAIJ. ). July 31, 1’368. Contract AT(45-1)-1830. 58P.tlw. CFSTI.

Fxpcrimental mrasuremrnte were made on a test lattlcr of eep-a!ahlc tubrs of fuel and target material in a Kraphltc-morkratcdlatt{ce in the PCTR. Measurements were made nf the lnflnitc me-”diurn neutron multiplication factor on a defined superqcll of threeuranium fuel celle and one Th02 target cell. ,The mcasurmf pa- ,remcters include data for two distinct fuel types in Iatt Iccs withand without coolant consisting of 1.25 VA% enriched urimlum fueland Th02 target at 77% theoretical deneity in separate proccsatubes. Determ Innt ions of k ~ were made with the coolant channel awet and dry and with two rflffertng fuel sizes to obtain an cstlmateof the ChanKe in rractlvity due to watbr Ioaa as a function of cool-ant and fuei gcnmct ry. (auth)

..22760 EXPERIMENTAL STUDIES OF U~-H20 LATTiCESOF UNIFORMLY ARR,AYED RODS AND CLUSTERED ELEnlENTs.Wajima, J. T.; Kobayaahf, S.; Yamsmoto, H.: Kikuchi, H.: Ohnisbi,T.; Mitmioka, K.; Yamamoto, K. (Hitachi, Ltd., TokYo). PP 67-72 of The Physics Problems in Tbermsl Reactor Deeign. Lomfon,BritIab N,uclear Energy. Scciety, 1967.

From Internettonal Conference on Phye’tcri Problems of ThermalReactor Deeign, London. See CONF-670607.

Lattice studies of uniformly arrayed UOZ rode and of clusteredeiemcnte of a nuciear auperhcat reactor were performed endanalyzed. Microparametera were meaeured end multiplicationfactors for the fcxir-factor formula with ‘s% epitbermal flrwdonawere obtained. Empirical formulae for mlcroparametere *emderived, and a method of meaeurtng the nonieakage prebabiiityis presented. The analysis of the lattice of tbe clustered fuel eie-ment is diecueaed. (auth)

6116 “ it2TWAT10ti sIfA PES IN 2%1- AND 2$W-THORRWISJi Efl-RLANKL;T CRITICAL ASSi?hlfll,lliS. Weiss. S. R.;Lchmnnn, P. Il.: Mltclwll. J. A.: Johnson, P. J.: Rusw?ii, C. D.:Whpnt, L. I,. (lV:ttls Atnmfc }’owrr l.ntI., West Bliffiin, lM,).Trnns. Amer. Nucl. Sac., 10: !Y37-8fNov. 1967).

!:rnm 151h Con fcrcncc on i{emote Sye)ems Technology nntlAtnm Fnir, Cl!lcngo, 111., Nev. S9, 1967. 8ec Ct>NF-6711n2.

22837 STUDfES OF SINGLE-RCiD LATTICES OF U~ (NAT-URAL AND ENRICHED), PuQ OR Th~ IN HEAVY’ WATER.Wikdahl, C.-E.; ”Sck6lowski, E.; Persson, R.; Jonason, A.;Anderascin, A. J, W. ~Aktiefmlaget Atomenergi, Stockholm).pp 103-10 of The Pbyslcs Problems in Thermal Reactor Design.London, Britieh Nuclear Energy Society, 1967.

From International Conference on Pbysice Problems of ThermalReactor Design, London. See CONF-670807.

~xtensive studies were carr~ed out on single~rcd lattices inheavy water. Fuel red composition, iattice pitch and (in somecases) temperature were the parameters vnricd. Buckiings, spac-tral tndices and conversion ratloa were measured. Tbe experi-mental results were comparod with calculated v~iues obtainedwIth the fcur-g rcup program CAROL, and the more advanced cellprogr’am F~EF, which ie baeed on multigrcup integral traneporftheory. (auib)

4104 RtACTI Uf l’liY.Y7CS PARAMI’TJ>R9 ~~r 2“ll@-Th~LAT7TCES iN D2(~. Wlnflwm, Hnnry Ii.; Trmrrey, Wlillnm J.fDrmkhavon NIIti,mnl 1A)!., llphm, N. Y.). Trans. Amrr. Nucl.%c.. 10: S$?%fifr+w. 1967).

Fr%m 15UI < onforem-p on Rmnntc Sysb.mf4 T[thriology nndAfnm Fair, chics~, 111,, Nrw. 5-9, 1967. See CON F-671102.

29

.

.

.

III. REACTIVITY MEASUREMENT

1967

42725 (ANL-7357) REACTOR DEVELOPMENT PROORAMPI{M1{ESS IthlPUftT, JULY 1967. (Argonne Nationsf LatJ., Ill.).Aug. 31, 1967. Contract W-31~lt19-eng-38. 148p. Dep. CFSTI.CRITICAL ASSi7hIBLIES— p{.rturlr~tiun m(.:1wirumentti iu Z Pit-

3, usr uf flssjonuble m:tl,. ri;ils fur; p(,rturl,.itlun measure-mculs in ZPR-3, use of Iwruu timl tuntalum for; flux mea-suremtmts in Z PI1-li, ad joint; Dupplcr effect mcnsurcmentsin ZPR-9

.,

38711 EXPER1hlENTAL AND ANALYTICAL DETERMltiA-TIC3N OF THE REACTIVITY WORTHS OF 233U,23SU, 236U, AND117NPMM pLES IN A SEfUES OF 235U–GRA IWITE CRITICALASS fi\lBf.lES. Bardes, R. G.; Glf.lette, E: M.; Nirscid, R. J.:Traylor, R. C. (General Ahmtc DIv., Get3eraI ~nmics Corp.,Wr Diego, Calff.). Trans. Amer. Nucl. WC., 10: 198-200 (June1967).

From 13th Annual Meeting of the American Nuclenr Society,Ssn Diego, Caitf., June 11–1S, 1967. See CONF-670602.

8061 SURFACE-TO-MASS AND HETEROGENEITY ~ F6ECTSON TfIE SpECIFIC REACTIVITY oF SELECTED hfATERlALf3 fNA FAST-NEUTRON SPECTRUM. Carpenter, S. G.; Mountford,L, A.; Springer, T. H.; Tuttle, R. ~. (Atomics Internatlonai,Canoga Park, Calif.). Trans. Amer. Nucl. Sot., 9: 50.f(Oct. -

1N9v. 1966).

35671 (ANL-73Z0, pP 107-15) COMPARISON BETWEEN}:XPERIhl E.NTAI, ANI) Tfi I.OR ETICAL fNTllGRAL DATA ONF}ST cRITICA L FACILITI1’S. CALI, A PROGRAM FOR GEN-ERATING “EFFk;CTIVk” NUCLEAII GROUP CONSTANTS f3Y ACfJI(RLLATl(JX !WET]i(JIj. Cecchinj, G.; Gmd~I, A. (C(jmitatoNar. h,n:ilc I,cr i’!luurgia Nuclcarc, Curnaccla (italy). Centro di$tudl Nuclcar[); Ddl fiorm, I.; Falcscl)lnl, B. (Comitatu Nar,ionalept.r I“Lnergia Nuclctirc, RoluLma fftuly). Ccntro di Culcolo).

In order to treat nimultuncoualy a large number of exlx’rlmcntaId::lo rcititive to a glvcn m:itc.rlnl, II program [CAI.1) has inxm writ-tcm which determines a new set of “tiffcctlve” mu]tigrcmp con~tnntacrmsl>tmt with thu cxpc. rlmcnts contihfercd and :Iti CIWJCas possibleto a rcfcrcnce dct uldalned hy Imwt-vuluc crltcrlu, Proj]t.r allow-ance !s j.flvcn to the unccrttilr!tleM of the rcfurcncc cross sectlo”~and to the Crr[jrti a~sucl!dv{f with the Intcgyal d;iln thenlsulvcy. ThItITi,ls all~,wsncc rcmovm must uf the difficulties encountered whencorrelating d:tta ol,ttiinwl in tirjsemhllcrn with sl,cctrul char; ((:tcrls -tlcs not wfflclt:ntly dlffurtmt from each other with rcslj(wl tu theprecision” of the expcrlrnental techniques. A syt,tcmutlc co]llp:tri-

aon between experlm’ental and theoretical dati re&lve to the crltl-cal facilities ZPR-Iff, ZPR-Vf, and ZEBRA 1s then performed. Thequantities so far considered are the reactivity and fission ratiosof Pu-239 and U-233 with respect to U-235. The theoretical pre-dictions are obtained using the APDA 24-energy-group cross-section set and the Russian 26-gTOup one. The new White data ofPu are also considered. The experimental results are correctedfor sample size and shape effect. The corrected APDA Pu vaiueaand the Russian ones are more consistent with the experimentaldata than are the uncorrected values of the APDA act, when propercorrections for sample size are introduced. A iist of 23 referencesis included. (autb)

14000 MEASUREMENTS OF VOID EFFECTS ON TliE.REAC-TIVITY. Chrysochoides, N. G. (Democritus Nuclear ResearchCenter, Athena). Chim. Chmn. (Athens, Greece), 30A: .137-42{1965).

Two experimental methods were used to simulate voide’ fn thereactor mederator: (a) Statfcal methed, in which air gape were

“ Introduced in the reactor mcderator, (b) dynamic method, in whichsteam bubbles were created in the reactor mcde rator. The effectsof the voids on the reactor reactivity were measured and the void

1

oefficlenta were evaluated. The first rnethed, which sfmulatescttcr the case of urdformly distributed air In the mcderator, givesccurate rcnults. The preposcd second rhethed, which simulatesettcr the cim,e of real steam bdbbie formation in the moderator,

simple and givee satisfactory reaulta for fair approximation.authl ,’

31

1967 Reactivity Measurement30202 DETERMINATIO~ OF THE EFFkCTfVE hfULTIH.,l- ‘CATION COEFFICIENT OF NEUTRONS BY THE MEASUREMENTOF THE DIFFERENTIAL REACTIVITY. DideIidn, T. S.; Slrishfn,B. P. At. Energ. (USSR), 22: 113-17 (Feb. 1967). (In Russian).

Relations between the effective multiplication coefficients ofneutrons in reactors and th6 experimental values of reactivity coef--ficlents, determined by measurements of differential reactivities,were established. Correction terme were determined in integ@form. (tr-auth) ,.

19469 (KFK-473) tNTERPRETATION OF DOPPLER COEF-FICIENT MEASUREMENTS IN FAST CRITICAL ASSEMBLIES.Fischer, E. A. (Kernforschungszeutnun, Karlsrohe (West G8r-many). Irte.tltut Arrgewandte Reaktorphysfk); wt. 1966. 22p.Dep. mn.

Anaiyttcal results are presented on Doppler experiments in~b{ch the reactivity change dve to heattng .9amPl@e in far3t crl~-cal aseembliea are meaaured. A formaflem ~s deveIoped wbfchaliowa calculation of reactivity changes due to eampie beating.(J. R.De),

40684 - “MEASUREMENT OF Tlifi l{EACTtiI+Y COUPLINGCnEFFICIENT {N T}{I? IOWA STATE UTR-10. ffendrlckeon,Rlchnrd A.; Danofsky, Richard A. (iowa Stata Untv., Ames). ‘pp 5flG-20 of CouplctJ Rencfor Kinetics. Chezem, C. G.; Koehler,w. If. (errs.). Co!legr Station, Tax., Texss A and M Preee, 1967.

From Amerlean Nuciear Society, Coupled Reactor Kinetico‘Conferenp, Coliegw Stxtlon, Tex., Jan. 2k24, 1967. See CONF-670107. t .,.,, . .-----

A emss-spcctrai denrdty method (or ol]lalnlng the reactlvllycoupllng cocfflrlcnt of a couplbri core reactor [n dcveiqm(J. Anexpcrlmcn!al mcamrrc:ncnl of the ratio rrf the rcactlvlty rmupllngcucfflclcnt to Iho mean generation time of neutrons In the core Isdcecrihcd, 6 rcfcrencee. (M. L. S.)

7923 MEASURED SODIUM-VOID COE FFfCIENT AND FIS-S1ON R4TIOS IN A LARGE ZONED FAST tiEACTOR. Kamm,It. A.; Katoj W. Y.; Main, G.; Rusch, G. K. (Argonne NatwmiLab., Iii.). Trans. Amer. Nuci. See., 9: 487-8( Oct. -Nov. 1966).

25730 CENTRAL Reactivity MEASUREMENTS ON AS-SKMRLIES 1 AND 3 OF T1lE FAST fiEACTOR FRO. Lunrkw,Stlg-Olof (Aktieimlaget Atomenergl, Studsvik, Sweden). Nu-kleonlk, 9: ltl-2S(Jun, 196’7).

‘i’hc mnctlvity effects of ~mull aampica of vttrkme materkiluhavo bcert measured by the pcrlod method a{ the core ctmtre ufAssemblies 1 and 3 of the fatjt zero power reactor Fl{(j. For somematcrlnia the re,activlty change au a funcUon of suml,l” siic h~iaitio,bcwr dctermitwd cxperitnentaliy. The core of Aaat.mbl) 1coneiutmf oniy of U enriched to 201Awhereas tie coro of .4M,embly3 wao difuted with 3L)%graphite. The rcauits have LCCIIcompwedwith cuiuttatod valuee obtdncd with a tmxxrd-order trwuiport-thooreiicai lwrturbailon mode{ imd ufiing dtffejrentfy shie{&d cruuuscciiont.i ticpcmting upon sump{tj size. Qualitative agrL,enwnt haSgwicraliy bcun iound, ulthwgh di~crcpw]eicd ~ti{l exist. TIIC spuc-trum pcrlurbalion caused by the cqjcrimc.nti arrangcjn’.nt hidbcwn analyzed aud found toberather imptmtut. (aut~

‘38689 FFTF CRiTICAL EXPERIMENT* CONTROL-RUilSTUDIES ON ZPR-3. @tg, J. K. (Argonne Nattonal hb., Ill.);Hess, A. G McVean, R. L.; Fwralanf, P. J.: Ukich, A. J.: Batrd,Q. L.;, Bennett, R. A.; Engetrom, S. L. Trane. Amer. Nuci. *.,10: 269-70 (June 1967).*

\~&~#thA Musl Mcetlng of the American Nuclcsr Society,* Calif., June 11-15,1967. See CONF-671N02.

7872 (GA MD-7Z30) NULL RKACITVfTY MEAktiREifF:NTSOF MULTIPf.ICATtON CIIARACTEltfSTiCS FOli IiIGli-TE \f Pf! N-ATIII{I; , CAS-(X301.1:1) l{KACT(~R COIiES IN Til E X1OI)1YIF1)1[’1’(;1{(. I{ITI(”AI, FACIIJ”rY. Nlrh,)ls, P. F. (Gr’rwrnl Il\nnmlc sCOIP., San I)lcjg), f’sllf. Grwy-rnl Aiomlc I)l\ .). A,tg ?3. I’ll,li.L’cmlrm,t AT(OI-3)- 167. 3fip. f)cp. mn. CFSTI S2.ftO CV, S0.30mn.

Mcn!n!rvmrnt.s of the mulllplit’allon chnrartcrlktlr-a for llTC}iwere mn!lr In thr modlflcd IIT(; R crllicni facl{lly. Thr mrih!xl ofmcnsurcmvn{ !nvolvcs cxprrimcn!ai tfrtcrminnlhm (If lh(~ IdI\sluaicon~tltumdn nf n unit’c%ii with a multlpilcnflon fnc!or of {me uiw-nit is In a spectral- etwironmcnt characteristic of an Inflnltc arra}cf cclis of the rtnme type. The urrli ceil then has required poisunmkfcd and the calculations of the pelaoncd ceii compared u Ithunitv. Tfreee meam.treinents are valuable for core eamnics with

mnlllplicnliun fnctrrrs at nrarly unity in the nhscncr I,f ,M,lwm.[J.t!.W.)

;7733 MEASUREMENT OF THE tiPPLER COEFFICIENTOF FAST REACTORS USING HEATED SAMPLES. Pucker.Norberf (Univ., Graz). Aiomkernenergle, 12: 169-92(M~y-June 1967).

The measurement of the Doppler coefficient of a fast reactordue to heating a eample 19 discusecd. Tbc suitability of multlgroupdlffuaion mcttms for this problem Is fnveetigatcd and results arepresc:)ted within first order perturbation theory. (auth)

34078 (f3NW L--442) EFFECTS OF U(_)zCRYSTA’f>l,lNE‘NINI)lNG ON IJOPPLF:R COfi FFICIKNTS C,\ IX.:I?l. ATI(INS FOR

.

.

FAST RfiACTOR SYSTEMS: Schcntcr, R. E. (Il:ltt,, Ile-N,~rtfJwcst, Rlchland, Wash. Pacific Northwcqi 1,11,.). .Iww1967. Contract AT(45-1)- 1830. 12P. Dep. CFS”rl.

‘rho change In tho f)nppicr crwfflclcnt due tO crymtn IIlnO hlndlnKeffects was studlcd for 2SCUIn n U02 iaiiicr! for faql rvnctnr ● v~-tems. The “weak. blndlng,”’ or ihe short com mmd nw If’us IIfrllme

rLSCN~) npproxlmhtlon waa used, where the ‘3 U atoms In th~ UOZlatilce are treated aa a free gas with an effect{ve temperature.Calculallone were made to drtermine the dependence nf effcctlvetemperature versus temperature using the experimentfti phonrmdlstrlbuliofl of Dolling, et u{. CbmparIeon6 were h{ao made with ef-fective temperature obtained arneuming a Debye model for thecrystal, It waa feartd that far temperatures above 300”K the effec -tive temperature dcpmrdcrite wan well represented by the Debye

. mode{ (~ Y620”K). The temperature dependence of the reactivitywnn calculated for the ANL critlcai assembly, ZPR-IIf, 47, withthe result ~hat Ipcorporatlnn 0[ the crystaiiinc bhrdln~ ●ffectecaused the,calculated Doppler coefficient (dk/dT) to diverge fromthe “l~T’) rule in the low temperature region, in qualiiatlve agree-ment with the exfmrimental mnuitn of Reynoids and Stewart. (autb)

.

196727739 INVESTIGATIONS UN THE RQSSI a EX pERiME~T.Schul /e, F.khard (Tr(’ivrlschv Huchschule, f)arm~tad~, Gerc)c I

, Nuklconlk, 9: 85 !17{f’’oh.1907). (In German).The Rossi n muasurcmcnts which arc In opposition to theory

wrro rit.s[. rllw(l. Results of Monte Carlo calculations show that thebn~is fnr tht, rfiscrcpmrckw Is not to I?r found in rvactor kinetics. IAn rxt(,nsivc analysis shows thxt the physical hasrs of the .Ros81,o vxpcriml,nt have not brcn [ormulatcd rigidly cnuugh up to thepmsvnt. The mean time pattern of a mwtron chain can be dcscrlbed ,thruugh a dr.caying t,xpnncntial function. Since only such neutronrlmins can he used exprrimcntally which lead at Icast to an event, ~such chains were preft. rentlally rrcordvd which lncrcase by anahot,c avcrngc numhcr of fissions. In this way,, onc of the cxpo- Im>ntial functions of averngc dcviatin~ time bchaylor was produced.This is not cormi(ivrcd [n the common theory. f3y the counting pro- ,CVSS. n new mrrdvl rcprcsvnlltion was ~lvcn and was dcvc]ovdformally. The thwirctlcal considoratiorm therefore It”ad to ROSSIn expcrlnwnts with spccinl conditions which give a higher ratiowrrl cwrrcl;itlon term and background. As an application of thefbssl a mcnsurcmvnts.: a method for the dctermiflation Of p/L wa.givvn in which no rcact]vity measurements ‘wc.rc nr.ccssary. Thethcwry of the Fcynman a cxperimc!nt was not used in the proposednew interpretation of the Russi a cxpcrimcnt. (tr-auth)

21660 THE EFFECT OF PLUTONfUM lSOTOPiC COMP051-TfON ON THE DOPPLER COEFFICIENT IN FAST REACTORS.Shnviv, G.; Yiftah, S. (Soreq Nuclear Research Center, Yavne,Israel). “ Nucl. Appl., 3: 213-16 (Apr. 1967).

The effect of PU isotopic composition on the Doppler coefficient,1s examined In fast reactmrs having different chemical compesi-t ions of the fuel and clifferent core volumes. It ta found that for ●glt,rw coce volume snd chemical composition the absolute valuenf Ihr Doppler coefficient incrcmen with increane of the smourrtof hi~h PU isotopes f(OPu, 7C1PU,and ‘t2Pul. (nuth)

196812006 (AN&7399) REACTOR DEVELOPMENT PROGRAM.Progress Report, November 1967. (ArgoMe National Lab,, 111.).Dec. 28, 1967. Contract W-31 -109 -eng-38. l’f2p. Dep. C FSTI.CRITICAL ASSL.MMLiE2i —reuctlvlty mcaaurernents for smali/

SUII,I, ICpcrturbtitione In ZPI{-3 fust; COIWmaturi:d samplesful X1]1{-:1 Abscnlijly S0 flist, tqwcific.it mub fur, rmdrup n( “F}’1 t In XPl{-3, compnnitirm of core for; Iitomlc cOncwntra-tlons uf ZPi{-9 ::srncmhlicrn 13-21, t u:wiivity wortiw of FFTFi.aicty rods In ZPR-3, culcui. dion of

24926 (A1’l~A 214) Q\lXIU~i..l{I,Y ‘1I:{”IINI{;AI. i’Iif X;JiKSS1{11’01{1’(1N Al:(:-!;IIfl Ns(l Ill;i) A(’”f’IVII 11.,s, S1.l.r]., MIif.;fl I:P1)1;( 1 All{l”If i5t 1967. (Atijml(. I]f]wrr Ikwcl,q]mcnt Aswxtqtes,Inf.., ilntr(,lf. Mlrh.). Crmtrnf I AT(II-1)-R65. 122p. [email protected] I“s’i”l.CRIT’ICAi ASSEM131JW- reactivity worths and reactfon rat4

ratios calculated for ZPR-3 and -4

Reactivity Measurement32969 (GA-6468) “‘ffESULTS OF HTGR CRITICAL EXPf2R1-M!iNTS DESfGNEfl TO MAKE INTEGRAL CHECKS ON THECROSS i3ECT10NS fN USE AT GULF GENERAL ATOMIC.Bardsm, R. G.: Gillette, E. M.; Nlrschl, fl. J.: Traylor, R. C.(Gulf General Atomic, Inc., San Diego, Calif.). Feb. 12, 1968.Contra@ AT(I14-3)-167. l17p. Dep. CFSTI.

Cross-section data nro presented for z~aff, ‘s(f, *U, ‘8U, ~TNp,212Th 2~9pu, .r~OpU,snd hron, the inttcr being U!icrf as a standard.Tho nculr~m npcctra in the flvo critical assemblies can i]c char-acterl T.rd by their mcnn fiesion cnargy. This ranj@ from 0.074CV In tirC/U-51)00 nescmbly to 12.7 CV in the C/U-432 aeecmbly.The ~oftcr epcctra pcrmlt, the study of cross scct[ons in the ther-mal energy range while the harder spectra emphasize events inthe epiihcrmal range. The comparleon between the calculated andmeosured, results for the abeve materlafa In the five core assem-blies shows the percent deviation of ihe calculated value for agiven matcriaf from the measured valuee, The percent deviationrepreeente” the average [or the different material Ioadtngs of eachmitteklai inves tlgated and fncludee en sllowsncd for the eetimatedoxperlmetdal unccrtalntlee. (auth)

35636 CF,NTRA1, REACTIVITY” CON~fif RUTI(JNS OF ‘Cm,2S!J>U AND ~~~tlIN A BARf; CfffTICAL @jEMf3LY OF PI,l’TCJN-SlllM METAL. Barton, Dnvld Maxweil (LYrI Alnmos ScientificLab., N. Mex.). Contract W-7405 -eng-36. , Nucl. Scl. Eng., 33:61-6(1968). (LA-DG9342) .

Centrai reactivity contributlone of gram-alzed eamplcn of 2~tCm,239Pu, and 2WJ have been obtained fn a fact critical aermmbly ofbare 2nPu In a spherical geometry. Resulting valuea are: 2(tCm =(127C ● 5%) centfr/g at.; 239Fu = (1393 ● 3%) cente/g at.; 2JSf-’=(701 + 2%) crmts/g at. From thcee data, the critical mace of a harenphcre of 24(Cm ie estimated to be (27.7 ● 2.5) kg at a deneity of13.5 e/cm~. (auth) .

33036 THE REACTIVITY WORTH OF SODIUM IN THE ZPR-.9PLUTONIUM Assembles 48; 48B, AND 49. Broomfleld, A, M.(Atomic Energy Eatahlishment, Winfrith, En&); Matlock, R. G.;McVean, R. L. Transj Amer. Nucl. Sot., 11: 240(Juos 1966).

From 14th Annual Meeting of the American Nuclear Society,Toronto. See CON F-660601.

22835 STUDIES OF BERYLLIUM OXkE-MODERATED RE-ACTORS USING MINIMAL QUANTITIES OF fVtATERfAL. COn-nelly, J. W.: Gemmeli, W.; Marke, A. P.: Tattersall, R., B.(Australian Atomic Energy Commlesion Research Eetabllshment,Lucas Heights, Ncw South Walea). pp 83-90 of The PhyeicaProblems in Thermnl Reactor Design. @ndOn. Br1ti9h ~ci~e$Energy Society, 1967.

FrOm [ntcrnationnl Conference on Physics Problems of ThermalReactor Deeign, Lnndon. See CONF-670607.

Smail fkO-mcderatcd subcritical aseemblie? fueled with aSUwc re studied in tic intccnai reflecto c of qn Argonaut-type reactor.Thoria was added in some casca. Measurement were comparedwith multigreup calculation, and the sgrecment was satisfactory.(auth)

32970 (GEAP-5S84) SODIUM-COOLED REACTORS FASTCERAMIC REACTOR DEVELOPk~ENT PROGRAM. Twenty ~iftft .Quarterly Report, November 1967-January 1968. (GeneralElectrlc Co., Sunnyvale, Cal if. Advanceg pro~cte OWratlOn)* “”.“..’Mar. 1968. Contract AT(04-3)-189. 112rI. DeD. CFST1.lJRANIUflf-2:i8 -cnptire crose section 0[, error nnn@l@ for ; ,,pLLITONKIht -239 — capture cross acctlmr of. crrOr nnnl~eia

for: flpsion cross flcctinn of, error nn81yeis for

33

1967

18563 “ FIfiT EXPERIMENTS WTH THE ZERO POWERFACILITY ECO. hage, W.; Hettlnger, H.: Hotunznn, H.: Metz-dorf, H. J. I ToselU, F. Atomkemenergfe, 13: 133-8 @r.-Apr. 1968).

A short d6scrlptlon is given of the.zero pwer facility ECO. itsrefcmnce fuel elemhtq U/19/12, .ansf a summary of the reeUUSobtained during tfwi Initial etart-qp experfmente. Reeulte of reaC-tlvlty measuremcnta on control elemente and on certain perturbedcore ‘conflguratlone are given, ,$ogetber wtth a Uet of the meaeured

,.kcktlnga of the reference core. (auth)

25105 MEASURING THE GEOMETRICAL DIMENS1ONS OFHOMOGENEOUS URANiUM-WATER REACTOR CORES HA~H43SMALL-SCALE HETEROGENEITIES. Kontrovsltll, S. N.; Leved-nyi, V. A.; Yeroehevtch, Q. I. (Irwt. of Nuclear Potyer Engineer-ing, Minek). Vestal Akad. Navuk BSSR, Ser. FIz.-Tekb. Navuk, ,No. 3, 32-7(1967). (In Russian).

The critical dimensions of u reactor, and the effecttve additionnf reffcctor can be determined by making re”acUvky nicaoure-mente on subcritical aaeernbiiea, and by noting a number of criti+cal states of the acUve core at varioue settings of the controlrods. Theee metiode were found to be accurate, -2% for Az-tively small homogeneous cores. The effective adgitlon bf reflee-tor and geometric oize ae meaaured hy the firet metbed was leasacqurate than that measured by the second method. The valuesobtained by botb methods coincided within the iimite of the ex-perin.ent.al errors. The method of meaeuring neutron fl~ dis-tribution wAe not applicable iti thie caae. (TTT)

. . . ,.

22821 (LA-DC-92i6) CRITICALITY AND CENTRAL REAC-TIVITY CALCULATIONS USING k:NDF/B D.~TA. LnBnuve, R. J.;fffiunt, M. E. (Lea Alamoe Scientific Lab., N, Mex.). [1968].Contrnct W-7405 -cng-36. ‘ 7p. (CONF-680307-23). Dep.CtST1.

From 2nd Conference on Ncutroa Croae Sections rind Teeh-noiogy, Washington, D. C.

‘A sciics of criticality calculations has been Perform&f for se-iccted cwcrimcntsd nsscmblice to test the Category I, ENDF/B ‘nmttron rfnta. These aaeemblies include JEZEBEL (piutoniumcorcl, TOPSY (enriched uranium core with, natural uranium ro-flcctor), and ZPR-3 Assembly 48 (plulonitsm fuel, soft spectrum).Central reactivity worthe were elao computed for severcl mate-rinis of Interest in fact ~eactor deeign. In the couree of obtainingmulti~oup constants for input to the Lea Alamoa Scientific Lib-orator$ codee ua~ in these c alculatlons, Several Ef4DF/B re-trieval end procea.ving codes were employed. Tbeee includeDAMMET, a code for-rearranging and-altering the mode of thestandard BCD ENDF/B library tape; ETOE, a code for preparingIn MCt library tape; and MC:, a code for generating rnultigroupconstants from m Icroecnplc ‘neution data. Calculationel resultehave been compared with experiment as weU aa resulte obtainedusing other nuclear data Ubrarlee. (autb) -.

React ivity Measurement. ...- .

15925 KIRNL-T31-1736) PROMPT NEUTRON DECiY.ASIJ R7’hCTIVTTY MKAS(IREMENTS IN SUBCRITICAL URA-Nl[ M ME rAI, CYI,INDEIW. Mihalczo, J. T. (Oak Ridge Na-tional Lab., Term.). Pch. 1968. Contract W-7405 -eng-26.35P. OCP. CFS’H. ‘

I Prompt mwtmn rfccnv conetante have been dctcrmincd for un-rr+lcctcd nnd unmorkratml suhrritlcal cylinricrs of cnrlrhcd ura-nium (03. 1S% 23%) by thr Rosal-a tcchniqiw. The cyl{ildpr dinm-r.tcrs wr-rc 17.77, 27. !34, and 38.09 cm and the heights, at these ,. . . . .dinmeters, vxr[crs from 10.184 to 2.548, 8.431 10 5.399, and 7,502

to 4.780 rm, respectively. The decay conetants agreed to within4$ with those measured by the puiscd neutron mcthed; the com-parison with the rcsulte of S. Iranspert theory calculations showeddtsnjzreemrnts as large as 20%. flmctivltles as much ao 33 tiol-Iars subcritical were detrrmincd fcom the prompt neutron de.:aycrmstant nt dciaycd criticality nnd changce in the prompt neutronfifelimp with cviinrler bright calculated by Sn transport theory.These rcaciivities agreed favorably wiih v-aluce dc{ermlncd by ●nanalog computer whose input was the response of nn ionizationchamber to power changce when an aascmbly was diaaaeembled

,~rom deinycd’criticality to a given. reactivity. (auth)

3s004 PROMPT NEUTRON DECAY AND”Reactivity kfEA-SUREMENTS IN SUBCRITICAL URANIUM METAL CYLINDERS.Mibzlczo, J. ~.. (Oak Ridge National Lab., Term.). Contract W-7405-eng-26. Nuc1. ,Sci. Eng.o 32: 292-301 (1966)., (ORNL-P-

i 3620).%ompt-neutmn decay’ conatante have been determined for un-

reflected end unmoderated eubcrltlcaf cylinde;s of enriched ura- ‘niqm (93.15 wt % ‘JSU) by the RoesI-a technique. The cyllnderdlametere were 17.77, 27.93, asxf 36.09 om and the hclgbta varied

‘ from 10. M4 to 2.548, S.431 to 5.399, and 7.S02 to 4.780 cm, re-epecUvely. The decay constante agfced to within 4% with thosemeaaured by the pulsed-neutrun method; the comparison with the

“ reaulte of S. traneport theory calculation showed diaagrc,ementoaa large ae 20’%. Tbe ratio of the prompt-neutron decay conatarlt

o of a cylinder at delayed criticality to Usat of a eubdtical cyllnder●nd the ratio of the corresponding ~rompt-neutmn lifetlmon wereused to obtain eubctlticaf ~acUvities ee great aa 33 dollara. TbeNfelimea were calculated usirig neutron fluxes from S1 traneporttbk.ory. Theee reactivitlee agreed favorably with vaiuen doter-mined by an analog computer whoee input wae the mepenae of ●n

●

ionization chamber to power changes when an aeaombly’ wee dic -asscmbled from delayed criticetity to a given reactivity, 11reference. (auth)

27466 (LA-DC-9404) REACTIVITY VALUES FROM THE “. oLASL CROSS-SECTION TAPE LIBfiRY. Miile, C. B. (LOS ● :..

LAlamoe Scientific Lab., N. Mex.). Ind]. . Contract W-740S-e5W-36. 3P. (CONF-660S01T12). MP. CFST1. “

From 14th Annual Meeting ,of the American Nuclear society.Toronto, Ontario.

Effects of computer approxlmationd oti reacfivtty determimtieotare diacpeeed. Computntiona of ‘central reactlvitiea in fant apec- “

‘ tmrn critical aseembli,ee are f.ebulated *S a finctfon Of Oeutro?energy grciup, thip shows reactivity dependence ‘on ●tergy. Corn-’.periaon of reectlyitiee, determhted itt this manner, allown neutrtm,cross section evaluation. (M. L. S.)

●

.-. .)“

.

.

.

34

1967

44895 (IN- l{lIi7) ANA I,YSIS OF AHM F MEASURE”Mk.NTSIIY (>NF-lllhll NSI(jNA[, hill I, TIGf{OUP DIFF(lSI(JN CAl,C!.l I.A -TI(lNs. hllllsnl,, 1). A. lIdaho Nuck2ar Corp,, Idnho i’all~),July I!ttifl. C[,ntrat.t AT(l[I- 1)-1230. 56p. f.kp. CFSTI.

l)cscrll]tlons{~[th(. Alihll:-l and ARMF-11 cnre lrradln~p forreactivity mcasurcmtmta arc given. Exfrcrlmcntal pror!ulurcs aregivrn. C~lm!l:dkmnl procwlurca nrrdcscrlbcd; r!!cr~rmrf !,thargygroup structurr~ nrr-listed. Normalized unpcrturlwd rwl fl,lxrs,sdjc,lnt fluxes. nnd al>w$rpth,n etatlstlcid weij@r arc Lnhulat(”d. Re-sults of mv?!mr!d nrrd rnlculaicd va\uca are shuwn grnphlcnllv.tiroup cross .rcllims .Inri r,.:tctlvltlcs arctabulntcd for walrr,II{,:!vvwatrr, lb.. C, hlg, Al, Zr, Pb, and fN. 12 rcfcrrnrrw.(M. L. S.)

35667 (X.\ A-kH-\lcmo-12288) SUR”FACE-TO-MASS ANDHETEROGENEITY EFFECTS ON THE SPECIFIC REACTIVITYOF SELECTED MATERIALS IN A FAST NEUTRON SPECTRUM.Mountford, L. A.: Springer, T. H.; Carpenter, S. G.; Tuttle, R. J.(Atomtcs International, Canoga Park, CalIf.). Mar. 7, 1967.21P. (COSF-6611101-57). Dep. CFSTL

From 14th Conference on Remote Systems and Technology, ‘Pittsburgh, Pa.

The reactivity w’orths of several, samples of U (of several en-richments), Th, Ta, and W have been measured In a neutron epec-trum charncter[zed by a mcdlnn fission energy of 63 kcV. Theresults have been used to dctcrmhre the depcndcncc of the trpccfflcworths on the surface- to-mnss ratio (S/M) of the samples. Thedependence on mrriohment hos also been meaaured for U withheterqgenwms mixtures of ‘~$Uand 2SSUshowing thnt the cffc,ctof using two mmplcs of different cnrlchmcnt wns lfttle dfffercntfrom that of ushw a corresponding un[form cnrlphment. The re-gctivit,” Offm-t “f t!,(-r~fli I.xpq”sj(j” W3S c“i(.,,lntc+ fro”, (he (s/M)dependence nrrd us~.vl (0 cnr!vrt !hc t,,tnl tctnlmrnlurc crwfflclr.ntd rmctivilv to ,~td!rin lhr cfft.ct of I)qpplor l>ron(i~nlng, (fluth)

32977 (NAA-SR -Mcmb12289) THE CONTRIBUTION OFTIIERMAL EXPANSION TO THE TEMPERATURE COEFFICIENTOF REACTIVfTY OF 2JSU METAL SAMPLES. ?@untford, L. A.:Sprin~er, T. H.; Carpenter, S. G.: Tuttle, R. J. (Atom{cs Inter-ItIIUOrinl, Cmroga Park, Caflf.). Mar. 27, 1967.’ Zsp.(cCaNF-650602-69). Den. C FSTI.

From Arncrlc~n Nuclear Society Ilth Annual Mectlng, Gatlln-burg, Term.

The rcnctfvlty offcct of thorrnalcxpa”tiion of ~l$u Mcta] hasix?cn. mcmurcd and calculated in a scrlcs of neutron energyePW’tra. ‘rhc correction of the meauurcd tcmpernturc coefficientof rcnctlvlty for this effect to obtain the Depplcr c(fect la shown[or one of thcNc spcutrn, The rcflults of temperature cocfflclentmcnm!romcmts with 2s0U nnd Th In thrsc apcwtrn are given. (auth)

26767 SPATIAL DEPENDENCE IN THE MEA~UfiEMENT OFTHE REACTIVITY IN A SUBCRITICAL SYSTEM.’ Ortiz, G.Lopez; Olarte, F, J. (Junta de Energta Nuclear, Madrfd).Nukleonik, 10: 329-30 (Jan. 1968).

The renotivlty of a heavy water -natural uranium carbide cylin-drical system was measured using a 150-keV Cockcroft-Waitonaccelerator as the ‘neutron pulsed source. Caiculatlve techniquesof Garells and of Gozant were used In which system ,response to aneutron pulse ts determined. (S. F. L.) ,

196A, Reactivity Measurement

47004 (A PfJA-216(Vcd.1)) ANA I.YSIS (IF SCNJIUM ftflAC-TIVITY M}:ASUfllihlk:NTS. VOLUME 1. CROSS SECTION F;VAL-UATION ANfJ fJATA TfiS’f’iNG. Plitcrle, T. A.; Pagu, Ii. M.;Yarnarooto, M. (Atomic Power Dmwiopment Ammclateta, Inc.,

.-Oetrolt, Mtch.). June 1968. Contract AT(1 I -1)-1365. 1(1411.Dep. C k’S’l’l.

Ar qnutyfdII of sodium reauttvlty measuremtmtn lU fadl I uttuturcritical aascunbllus Is preuontcd. Voiume U presmtu lhe wNIIuni -vuld UnUlyHid. in Vol. 1, omphatilti Iti placed on cruun tieulllmevaluutiou and datn testing conducted to eetatbtluh the W:CUrm: y ofthe croaa acctlcm dula uucd for the ctilculutimtu (#f Vt,l. 11. Vt,lurne.I tfc!ncrltwa thrn evuiualkm d the cI’uMtItitwllon dJi.1, tcbtiug of thedata by cumparinon uf cuiculutlwu! with urtegt al expel Iumm uwa -qurementn, and an examfnnUon 01 mtithwlm umcd for crlUcal as+sembly Calculatlona. Neutron Croae buctkms Important for thesodium anaiysla have been evafuatcd as modificatlnos to the ENDF/ ‘B data file. Calculations of criticality, reaction-rate ratios, andmaterial worths ueing both the iiNDF/B and modified ENDF/Bdata have been made for ZPR-IiX Aaaembiiea 48, 48B, 49, andZPR-VI Asscmbliea 2 and 3, The modified ENDF/B data are foundto be over-reactive for these assemblies by 0.2% to 0.4% Ak whiletbe ENDF/B data are under-reactive by 1.3% and 0.7%, for thez~~~ ~d z~~u-fueled assemblies, retipectlvely. fn generSl, themodified data yield better agreemfmt with ,expc riment than theENDF/B data. Methoda cxsmtned lnqlude rctionance seif-shieldfngtechniques, variations in number of groupa and geometrical rep-resentation, an investigation of, absoiute central worth discrep-ancies, end the usc of cell-homogenized cross sections. Tbe cell-homogenizrxt cross aectiona are obtained aa averagea overtranapon-theory caicubitions nf the sputiaf diatributinns of tbeflux in the platee forming a cell. These calcuiatlonu iluiicate thatthe plate heterogeneities may have significant effects on the realand adjotnt flux spectra. (auth)

47005 (APDA-216(V01.2)) ANALYSfS OF ~ODIUM REAC-TIVITY MEASUREMENTS. VOLUME 11. SODiUM VOID CAL-CL’LATTONS. Pitterle, T. A.; Page, E. M.; Ysmnmoto, ;1.(Atomic Power Development Associates, fnc., Detroit, Mich.).

i June 1968. Contract ‘AT(ll-1)-665. 104P. Dep. C FS’fT.The second of a two-volume rcpnrt on .an analy61s of sodium

1 reactivity meaeurcmcrits in fast rcacior crltlcal nsrmmbl {M isprcacn~rd. Volume 1 dcscribca the cross section cwnhmtlon anddntn testing conducted in support of the aorfium VIJMannlyscs.Volume 11dc.scribes the methods of caiculatirm and the cnlculatcdresults for nn analysis of endium void mc~urcmrnts performedin ZPR-UI Assembllcs 48 and 48f3 anrf ZP1{-VI Asacmblics 2 nnd3, “The detailed void mcnaurcmcnts in tho atwwmbllcs havo hconcalrulntcfl uriin~ the hf};Nf)F/R crrrss rwctlwr dnln drwcribwl In

I

Volume f, xnd l~l(litl(mul cnlculntimr8 have l~{wvrwith tho l; Nl)F/fldata. The baaic method of cnlculnlitm is port!! rbntlon theory In one-nnd two-dimenrilonal diffusion thvory. Mcthtxf~ cxnmfrmd includovariations br rcsonarrcc aclf-shic}rftnp. tcchniqucri, number ofgroups, variations of pcrturbntlon theory inclu(Jlng cxnct perturba-tion theory, transport thermy, and hctcr~genclly constdcrations~For the hetcrogcncity anaiysis, cell-homogenized cross sectionsare obtained by ftux-weightbrg over the CC1l using trMtWOrt thcerycrdculatlorm of the apatiai flux distributions. Ovcraii calculationsof the void reactivitics with the MEND F/B dnta show better agree-’ment with cxpertment, particularly for the 2?Pu-fueled aascmbiieS.For centrally voided reglona, the hlfiNDF/ff data yieid the follow-tng qualitative agrccmcnt with experiment: 25’b Icss prdtivc thanexperiment for Assemblies 48 and 48f3, 15% less negative than ex-periment for Assembly 2, and 25% more negative than expcrimeqtfor Assembly 3. Rcgfrms with large Icakage contributions tend tobe conslatently underestimated by about 15% with maximum di6-crcpancies of 2\ ’1,for aII asscmbiics tanaIyzcd. Heterwpne!ty ~dtramqwrt theory effrwta on the vrdd rcactlvitlcn arc found to benntahly large for Aeflcmblv 48. (auth)

35

1968 Reactivity Measurement

53292 EXPERIMENTAL AND THEORETICAL STUDIESOFf7FL\CTIVITY COEFFICIENTS OF IMPORTANCE FOR FAST RE-ACTOR SAFETY. TIren, Ingmar. Goteborg, Chalmers Tek-niaka Hoegskola, 1968. 23P.

TheaIs.A oummaryla madeof6 published papers by,theauthorandke-

authora on the followlng subjects: meaauremont.ao danalyaia ofrcactlvlty e[fecta In empty channels in a faat reactor; tablea re-lated to the mean aqum-echord lengthln rlghtparalleleplpeds;studies of the reactivity of polyethylene In the fast reactor FR-O;studies of the effect o[beavywater In the fast reactor FR-O;activation Doppler meaeurementa on238U and2SsU In some faatreactor spectra; and comparison of theoretical and experimentalvnluca of theactlvatlon Doppler effect In some fast reactor apeotra.(sWed) \

1873 STUDfES OF THE RATfO OF 21:U CAPTURE AND~~~fJl?IssIcIN CROSS SECTIONS IN T1fE FAST REACTOR lJR-O.Tiren, L. L (Aktlebnlaget Atom6nergl, Studsvik, Sweden).Nukleonik, 10: 141-8(1967). I

Measurements of the ratio of 2SU canture and ‘MU fiaaion cronaaectiona have been made in five cnrea of the fast zero energy re:actor FR-0, correspaxiing to thr,ee aubetantialiy differbnt neutronapcctra. The experimental reauita were calibrated by measure-ment in a thermaf spectrum, for which the cross fiections in-voived arc accurately known. The capture rate In 2~~ waa dete~t~ .by counting the 211Np~.scUvity,Of iriadiatcd foils Using thq Y-X-raYcoincidence technique, rmd the fieaion ratin in ‘% was obtainedfrbm the counting rate of a small fieaion chamber., The experi-mental reaulta were reproducible to within abnut 1%., Sy@ematioerrora due to the hete rogeneoua core loadings and other eff cctsadd another 1 to 2% tn the net uncertaintica. The measured valueaobtslned at the centers of the coren are in gocd agreement withresuits of muitigroup calcuintions. (auth)

!36

Iv. NEUTRON FLUX SPECTRA

196712247 NEUTRON SPECTRUM MEASUREMENT IN A’FiWTCRITICAL ASSEMBLY. Bennett. E. F. fArgonne Natloml Lab.,fll.). Nucl. Scl. Eng., 27: 28-33 (Jnn. 1967).

The neutron spx!trum at the center of a large, dilute fast reac-tor was measured oier the wrergy.interval from 1 krV to 1 MeV.Resolution of the measurement was about 20% (FWHM) except atthe lower energ!es. Errors In the measul cmmst arc doscrlbdd anda comparison made of the mcaaured result with a multltmergy -group calculation. There exists fair agreement between the mea-aured spectrum and the multigroup calculation. (auth)

35686 “ (ANti7320, tip 477-80) SPECTRUM MEASURE-MENTS IN A fARGE DILUTE PLUTONIUM-FUELED FAST RE-ACTOR. Efcnnett, E. F.; Gold, R.: Huber, R. J. (Argonne Na-tional Lab., Ill.).

Spectrum measurement have been made at the center of theZPR-3 Aqscmbly 48, a large, dilute, Pu-fueled fast reactor. Theenergy distribution of fra~mrts from the 8Li(n,rr)t reaction andnf protons rrcoi 1ing in a R proportirmd counter CM be hlt erpretedin terms of the neutron-energy spectrum. The resuita of mea-surements with the two techniques arc compared, and the agree-ment in within estimated errors. (auth)

38687 EXPERIMENTAL NEUTRON-SPECTRUM” COMPARI- ,SON FOR A ZONED AND A HOMOGENEOUS FAST”CRITICALASSEMBLY. Beonett, E. F. (Argonne Nattonal Iab., U).Trana. Amer. Nucl. SoC., 10: 271-2 (June 1967).

From 13th Annual hlcetlng of the American Nuclear -let’y, ‘san Diego, Callf., June 11-15, 1967. See CONF-670602.

27798 (GEAP–5340) NEUTRON SPECTRUM MEASURE-MENTS fN A FAST PLUTONNJM ASSEMBLY, ZPR-IJI AS.SEM-BLY 48. Brown, P. S.; We!tzberg, A. ‘(General Electric Co.,Sunnyvale, Calff. Advanced Products Operation). Jan. 1967.~rmtract AT(04-3)-189. 28p, Dep. C!FSTL

1 kc n,wtro!i !moctrum has been meaaured in ZPR-H1 Assembly4R. n rfjlut(,, Pu-fueled faat reactor. At the core center, a protmrrcwll spectrometer was used to cover the energy range from 14kc\’ to MeV and resonance sand@i6h dctectora were uacd to crjverthe range from 18.8 eV to 2.95 keV. fn the U-239 bktnkct, a protonrecoii spectrometer was usedto cover the energy range from 4kcV to 1 McV. (auth)

“35688 (A Nf’-732lI, PP 486-Y) CMMMINT UN SPLti”i’’i WhlMEASUREMENTS iN A LARGE, DILUTE PLUTONIUM-FULLEDFAST REACTOK, Brown, P. S, (Gerwral Electrtc Co., Pieaa-anton, Culif. , Nuclear TectuloiogY Dept.).

A gencrntizmi description of a prokm-recoii spcc’tronwter for. n(utrun apcctr urnmmmm(vrwnts 18 given. lxpcrimcnls utilizing

tili~ Mpmlrwnctcr oru briefly (flww~st,tf. Colnjmriwns of t}lurnl~(,ctrum ut coru ccntcr of 7.PR-3 und in tbc blmkct o! XPil-3ore s)wwn tyv!Iilicuily. (M. L. S.).

14027 FAST-NEUTRON SPECTRA IN WATER AND GRAPH-ITE. Harrle, L. Jr.; Sherwond, G.: King, J. S. (Univ. of Mich-igan, AM Arbcr). Nucl. Sei. Eng., 26: 671-3 (Dec. 1966).,

Measurements of space-dependent fast neutron spectra in waterapd graphite at 2.0 and 12.0 MeV for fiuxes dlrectkd normally tothe Ford reactor core face with fwnr-t rationa up to 60 Cm are re-ported. Comparison of the mcam!remcnt vaiues were made wlfhthose calculated using the shleldtng code NIOBE. A eolid-stateproton- recoil telescope waa used to meaaure neutron energiee.k7.R. D.) o

32365 hN5-SD-2; Paper 3) fN-CORE EXPERIMENTS~u:e; AR9L; “SANDWfCH” FAST NEUTRON SPECTROMETER.

,.. (Argomse National Lab., Idaho Falla, Idaho). d 8p..’ The use of surface barrier detector- lfthIum-6 sandwiched fast

neutron spectrometer for In-core measurements in the ZeroPower ,Reactor III Aaaembly 46, a zoned fast critical having aOoft (for” fact reactora) neu~roq ener~ spectrum, and the ArgonneFaat Source Reactor la described and the data obtained are pre-sented. (B. Q. D.)

‘3e21~ FAS-t-NI il.ri~f IN :JWV.TRA fN A lxPfxTED-m7ANfIJhf $4fJ}lEr{F.. Moore. N. A.: Neilf, J. M.; Oozanl, T.:RuaIM?U, J. L. Jr. Kkrw-ral Afnmfc Dfv., Generaf ‘t)ynamicaCorp., S~n Diego, CnI1f.). Trans. Amer. Nuc1. Sm., 10: 267

, (Juno 1!)G7).From 13th Annual Mectlng of the AmrmIcan Nuclenr Socfetyo

.Rsn Dlcgo, Callf., June 11-15, 1967. .S+e C(JN F-670602.

37

196740346 (RPI-328-87, PIV22-59) FAST NEUTRON SPECTRUMPROORAM. (Rensselaer Polytechnic Inst., Troy, N. Y.).

Information is given on the design and development of a sphcr~ical lead electron target for use as the neutron source in fastamemblles. Mcasurementa were made of the neutron spectrumfrom a 40 x 40 x 38 in? Imn aascmbly pulsed ~.viththe lead target.The spectrum of neutrons from several re-entrant holes in theiron aaaembly were measumd by time-of-flight’ using n lgBtC -Nn2 detector. An effort was made to fotmulatc the ndjoint fastreactor apect.rum, and an appllcatloo ie given for q rcprcscnta-Uve oxide core. A variational principle Is developed for the dc-tertninatlon of decay constante in pulsed fast neutron assemblies,A group conatantn averaging procedure for few-group importance-functloa and reactivity calculatlone in fast reactors le preeentetf.A stx-group importance function calcqlatlori is given In graphicalform for GODIVA uelng importance-avcragad and flux-averaged ‘group conetante. (. S.F.L.) ~

“ 30247 (AERE-R5347) THE DETERMINATION OF THEFAST-NEUTRON SPJiCT1{UM IN POSITIO~S IN THE DAPHNEREFLECTOR. Silk; M. G. (Atomic Energy Research Eetab-’llshmcnt, Harwell (England)). oMu’. 1967. 30P. Dep. CFST1. .UK 4a. 6cf.

The difficulties Inherent in npectrum determinations tn reacto~,at posltkma remote from thq c“ore center are considered, and thesuitability of lLi and ‘lIC semiconductor sandwich spcctromctomfor It,ia work Is dlncuurn[d. Slwctr~ ob!uincd In mahy poeitione inthe I)APIINE rctlcctor arc comp~rcd with calculated epcclra. ,(authj ,., .. . .

35687 (ANL-7320, pp 481~;) A COMMENT ON TiiE COM-],A[{lSON OF l~{EO1{ETICAL WITH EXpt;l{[MENTAL NEUTRONSPECTNA IN FAST CRITICAL ASSfiMflLfES. Trnvclll, A. (Ar-gonne National Lzh., 111.).

The expcrlmcmtal data obtained by Bcnntitt in the mcmmremmtof central neutron spcctm In fast criticnl nmmmbllcs huve n reso-Iutiun of 15 to 2tJ’L In energy ovor tho energy range, which rxtcndeapwuxlmatcly from 1 keV to 1 MeV. The high rc~olutlcm, com-birwd with the Mmnll WLlrntlctd error of tbti [I:tta, m:lkc~ it posei-Me w mcarnurc!, in addltlcm to the macroscopic twhavior uf the ‘neutron spectrum, some of tbc mlcrotmoplc variations of Uw spee-trum tit thusc energies for which rtwcmwrccs of the llgbt t!lemcnt~cause bhurp vm’ltitlona of the tranaport crnw rncctlon. The gr@erreaolutlon of the ttxpertmeotal spectra raises tbe queetion xa auhow accurately the present analytical methods can predict the mi-crcmcoptc variations of the spectrum, md adda considerable inter-est to the cotnpariaon of experiment with theory. The reaulto oftwo such comparisons are shown in which some detailed experi-mental spectra were matched to eorreeponding hi@t-resolutioncalculations. A 1iet of 14 references ia iacludcxf. (autb)

19684433 NEUTRON SPECTRUM ME”ASUREMSNTS IN ZPR-3,-6, AND -9 USfNG HYDROGEN-RECOIL PROPORTIONALCOUNTERS. Bennett, E. F,; Gold, R. fArgonne National

,hb,; RI.). Traho. Amer. Nuci. .20c., 10: 577 fNov. 1967).Frum 15th Conference on Remote Syeteme Technology and

Atom Fair, cbtce~, Ilf.,, Nw, 6-9, 1967. Sce CONF-6711O2.-.

Neutron Flux Spectra37276 (AERE-R-5364) MEASUREhlENTS OF FAST NEU- oTRON SPECTRA IN REACTOR MATERfALS. Cotitee, M. S.;Gayther, D. B.: Cbode, P. D. (Atomic ,Energ’ Reeeerch Eetab-tfehment, Harwell {England)). Feb. 1966. , 36p. Dep. ‘~FSTI.UK 8e. Od. ,

A series of neutron energy spectra emerging from apbericafshelle of tmtural uranfum, polyethylene, graphite and mdlum weremeaeured in the energy region 300 eV. to 6.5 MeV. The Ume-c4- .

‘ flfght methcd was used with e 60-m path and a pilse scurce offact neutrons provided by the 4s-MeV linear accelerator. Thesmrce wee located at t.fw”ccntrc of the shell and spectra leavingthe purface at O and 45” to a radhts vector were determined. Inaddition a few meaeurementn were made of spectra in the O“di- .,rectton” from different penetration depthe fnto tbb ebell wall. Thesource wns designed to emit neutrons iaotropically; and the atm ofttte meatmrementtt was to @ovtde apedtrq in simple mie-dimen-siottal wstem.e fxt order to text tfm nuolear data ,aets ueed tn reaa-tor cnlculationn. The cxporlmental method to doecrlbed In detali,nnd some compnriaons bneed on dlncrete ordinate solutlono ti fhe‘uIlt zmimn equal Ion are preeented. (autb)

iK3425 NEUTRON PROPAUATfON IN URANIUM DIOXfDE.PART I. SPACE-ENERGETIC DISTRIBUTIONS OF NEUTRONS.Goluber, V. L; Oolyaev; N. D.; Zvonarev, A. V.; Zizin, M. N,tKoleganov, Yu, F.; Nlkolaev, M. N.; Orlov, M. Yu. At. Energ,(USSR), 2~ 292-7(1968). (In Rue61~). ,

The experimental results of the neutron icducad reactfon veloe-itles in a large block of U02 (dloxfde reflector of BR-I reactor)are presented, The neutron specthun in the farge UOt block IsInvestigated by the time-of-fllght method and 6andvlch technique,The reaulte of the mcaeuremcnts are compa~cd with the calcofa-thme of tbc neutron propngntlon In U02 by 26-group net of con-sfnnte. The retmlts glvc the Puqnlhillty to eetimate the accuracyof the set of conetanta and catculatton metbuda. (auth). .

7619 ME ASUiiEMENr OF itSACTOR NLXfTRtJN ENERGYDISTRittUTIUN Tu-~omv. Kuhhlcvich, v. I.; Trjhuvo L. A.;‘rrykov, O.. A. At. Energ. (USSli)O 23: lY1-5(SePt. 1967). (inRussian) .

.The spectra of the reactor investigated were measured at en-, ergiea up to 19.5 * 0.6 MeV using a aclntillation spoctromcter wltba stilbene crystal and dlscrlmimition of tbe y htdik~~~ht duringthe excitation uatng flltere of lithium hydride (21.4 g/cm21 underconditions of g-nod geometry, Sumeueviatiuns of the modsurcd tm-ergy distribution fro’m tbe calculated and cxpcrlmcmal flti$loncspectra can be explained on account of the interaction of neutronswith the materiala of the active zone. With transmission eecf -flcienta up tc 10-8 to 10-4, the total cross scctiun WA m.”.isurcdfor water, carbon, and lcmd In tbe cuergy intmw:d from 1 to u McV“with errora of 2,5 to 3% at 1.5 ~ ffu . G MeV and a tu u . N Eu~VMeV. Tho total cr6ae tioctiou for curlk)d ami wutcy M E.> 2 MuV

,.- -,.,satisfactorily ngreee with publlahcd ‘data: For Icad nnd watcf’ be- “low 2 MeV, the alxee of the cross ecctione nre Iowcr (in comparis-on with the data for thick sampleel, which iS cxplainti by ~opacun~ of neuatrons throu~h the minimum VOIUOof the crona tmc.-” ‘Non. For lead In the energy r.mvgc nbovc -3 McV, n tendency toirrc~laritlcs wqn observed. The dcpmwfcnce of the huntncaccnceof the sttlbenc crystal on the energy made it ponnltde tn dctcrmlnetho scattering from cnt?mn eamples. (tr-auth)

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38

1968

50620 ) EXPHZfhfENTAL DETERM1NATION OF THE AMOUNTOF FA~ NEUTRONS IN THE FISSION SPECTRUM, Nnsyrov, F.:Stnlbnrskil, B. D. DoId. Akad. Nauk SSSR, 180: E36-8(June 1,i96~). (In RussIan).

If a small amount of moderator in contained In the reactor cor.,the rrxwtor neutron spectrum may be used tm sturfy the spectralpreperttcs of fisalon trcutrona. This problem wm Inveat{gatt?dwithin the core of a fast reactor opcratbrg wfth highly enrichedlt$u; the core also contained 20% Fe, 10% Mo, and 10% 2’8U. Theneutron spectm were invcst[gated In”the 0.6 to 24 McV region bymerm of thrmdrold detectors. F\88ion chamber dctermhrationaand activztton studlea were also made. It was found that below3 hleV, the reactor epectrum dlNcra irom,tbc flerdon spectrum,this IS due to the low cncr~ transltloos of ncutrona cnuecd bytnrlastic processes. Above 3 MeV,’ the spectra are fairly stml-.hr. The e}aporstlon model charnctcrlzcs the ffeslon neutronqwctrum up to 24 MeV; it rernalna to be determined how far thisrange extends. (TTT)

29829 IGA-9551) FAST NEUTflON SPE;TRA’ ~M-UL-TIPLYING AND NL>N-hf[fLTIPLYING MEDIA. Nc{ll, J. M.:ffllsscll, J. I.. .Ir.: Moore$ R. A.; Preskltt, C. A. (Gutf GeneralAtomic. Inc., Son Dir-Ko, Cnllf.). Feb. 23, 1968. Contra&tAT(04-3)-167. l?p. [CON F-680307-33). Dep. CFSTI.

From 2nd C’onference on Neutron C roes Sections and Tech-nology, tVasbington, D. C.

Fast nrutron spt.ctra wcm measured at varloU8 p081t10ne in8phcres of depleted uranium md 93.2% enriched uronlum, andthese dltx were uacd to pro~irfc’ integral checks on the accuracyof neutron cross sections nnd computational methods. The datarover the energy range between about 10 keV and 16 MeV andwr-rc obt:ttned using three flight pmth Icngths, 45, 50, and 210 .metr-rs. Thv detectors used mmsistcd ,,f a S-In. diameter NE-21.{ proton-rtwoil detector for fa8t neutrons and a S-in, diameterNE-90q lithium ghss detector for intermediate energy neutrons. ‘The pulsed cource for the measurcment8 W!L8obtained by im-pinging the beam from the Gulf General Atomic Linear Electron.+ccelerator onto tung8tcn or uranium targei8. Several different!Jpes O( calcuktlon have been msmparwi with the measurements,tncluding muItigroup trrmspert theory, and two different acts of

“ cro~s sectlrms have been used. The meaaurcd spectra In the 2S6U8phere are consistently softer. than the calculated vaiues. Themeasured spectra in the ~aaf-l8phe~e are accurate enough to permitone to choose the better of the two cross section sets. (aut~

33031,

FAST-NEUTRON SPECTRUM MEASUREMENTS IN’THE CORE AND REFLECTOR OF ZPR-3 ASSEMBLY-51. .1Powell, J. E. (Argonne Natlonai Lab., Idaho Fali’s, Idaho).Trans. Amer. Nucl. SW., 11: 217:lE(June 196W.

From 14th Annual Meeting of the American Nuclear society,Toronto. See CONF-680601.

.

30302 (GA-6377) FAST REACTOR SPECTRUM MEASURE-MfiNrS. Quarterly Progres8 Repert for the Pericd Ending Oc-tober 31, 1967. Preskitt, C. A. (Gulf General Atomic, Inc..San Diego, CalIf.). Nov. 21, 1967. Contract AT(04-31-177.16p. Dep. C FSTI.

con~truct{on of the Subcritical Tinfe-of-Flight Spectrw Faciiity.(STSF) is dcacribed; pFoblem8 fmctnmtered are discu88ed. An in-ventory of core materials present for loading tbe STSF i8 tabulated.Core and reflector compcaition for STSF- 1 is given; reactivitiea ofvaribu8 108ding8 are tabulated. Neutron epectra am shown forvarioue Iocatlons with respect to core content. Reactivf’ty traneierknre8ulUn$ from unintentional criticality whiie clo8ing the bed8 areshown as a function of time. O$L.S.) . . .

Neutron Flux Spectra

32452 lNTERhfEf)lATf? -ENf-3{fJY FAST IIF;ACTf)R SPEC-THA Dy”TIME-OF-FLIGfiT. Pmskitt, C. A.: Nclll, J. M.:Stevcne, C.,A. (Gulf G!?ncral Atomic rnc., Son Diego, C@ilf.).Trnns. Amer. Nucl. Sot., 11: 21(i-17(June 1%8).

From 14th Annual Mectlng of ttte American Nuclear Sodety,Toronio. Sec CON F-G30601.

p~oQff (OA+715) FAST REACTOR SPECTRUM MP.A-SUREMENTS. Annual Progress Repert for the Period EndingAprli 30, 1966. Preskftt, C. A.; Nelll, J. M.: YfJuw. J. C.(Gulf Generai Atorriic, Inc., San Diego, CalIf.). June 3, 1968.Contract AT(04-3)-167. 4flp. Dep. CFSTi.

A description of the STSF 8plit-tabie aimembiy 1s prceented.The first core loading for the assembiy, deaigrtatcd ST3F- 1, isdo8cribed. Deacrlption of the experimental eiectronica is pre -bcnted. Data reduction procedures are analyzed. Spectra mea-surements for intermediate and fast neutrone are prcaented.(fJ.c.c.)

39548[

(R I-32ti-123, w 1’6-25) FAST REACTOR PHYSiCSEXPEIUMEN AL. (Rensselz’er Polytechnic Inst.. Troy, N. Y.).

The anaiyais of time-of-flight measurements of ftist neutronspectra in depleted ursnium was continued, and compAer pro-grame were developed for ansiyzlng time-of-flight data on fastneutron spectra. Pieiiminary re8u1ta of measurements of p8rniti0n-dependent fa$+t neutron spectra in Iron are ai80 reported. (~.C W.)

48424 (RPI+2tl-133: pp 35-55) FAsT REACTOR PHYSICS:EXPERIMENTAL. (Rensselaer pO1@ech~c inst. ! ‘~y~’. ‘.)”

A 8eries of po81tion+ep8ndent fa8t neutron 8pcctrum measure-ments in rectangular assemblies of Fe and depietcd U wa9 per-formed; comparison were made with theeretlcal predictions.Preilmbrary studies of an CLi glasa detector for measuring inter-mediate neutron energy !IpeCtRI were britiated. Some dcvciopmentain detectors and associated electronic equipment for measuringfast neutron spectra are, alse summarized. (D. C. W.)

39

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v. NEUTRON CROSS SECTIONS

1. Sources of Data

1967

19151 fNAA-SR-Meme12315) THEATOMICSINTERNA-TIONAL EVALUATED NUCLEAR DATA FILES AND ASSOCIATEDCOMPUTER PROGRAMS FORTHEAU:OMATED PREPARATIONoF ~LTIGRoup Constants. Alter, H. (Atomlcslnterna-tiOnalo Csnoga Park, Cnlif.). Febo 24, 1967. Contra~tAT(04-3)-701. 29p. Dep. mn. CFSTI$3.00 cy, $O.65mn.

IrrputrfaL~ from the Atomlcs International Evaluated NuclearData Filc(AIENDF) tape areprocesscdtoglve spectrum-weightedgroup-avcrn~rd neutron cross scctlons”and o~h~rq”a~t[tl~?r~.qulrr.d forthcriolutlonof thcnctitron trana~rt cquatlonbymultl- ‘group dlffudlon wtdt ransport thcory,methorfs. ‘Nrc calculation ofmultlgroup flopplcr-broadened cffcctlve rcrionance Integrals andcross sections In the rcaonancc rcglon for a hctcrogcncous orhomogcncou,q resonance absorber lsbasdon thcsinglc-level ,Brrlt-Wlgncr theory with no ovcrlapplngof nelgbborbrg rea -onances. Inelastic and elastic scattering transfer matrices arecalmllntcd uxirr~ differr.ntial scnttrring cronn acctlon data stur don the AI ENIIF Anm!lar Dlqtrihutlon Data Tape (ADDT). Multl-group llt)rarivn nrepunrl)cd Insmyof the formrnt.q rcqulredbyth- mrc-dlmonslrmal multigr(,up (!{ffuslon Urcorycndrs, ULCER,FAIM, I: AIM-CELL, CAESAR, and CAESAR lV; the one-d\ men-nlmml multlgroup .% lranspnrt theory code, DTF; ad the .epbc-trum codma, FORM and AfLMOE. (auth)

33852 (EAt4Dti5btu)) THIHD BIENNIAL itEPORT OF THEACTIVITIES OF THE EUROPEAN AMERICAN NUCLEAR DATACO~MITTEE. Bretcher, E.; Batchelor, R.’ (Europesn-AmericmNuclear Data Committee). May 1966. 10P. Dep.

The actwities of the European-.imerican Nuclear Data Coni-mittce between J+rtimry, 1964, and Jwmary, .1966, are summ~-rizcd. (D. C. W.)

28149 (13NI-50061A) SIGMA CENTER: NEUTRON CROSS -

42520 (UNL-50061B) SIGMA CENTER, NEUTHON CROSSSECTION COMP1LATION CENTER SCISR~ NEWSLETTER.p~T B. I~ToPE LISTING. fBrookbaven Nationaf Lab.,Upton, N. Y.). June 1967. lo’fp. Dep. CI?.STI.

A Iiating, arranged by isoto~, is given of reference to pub-llshud and other material on various neutron cross sections. Thecro.vs-section types, dates of Publication, and neutron energyranges arc included. The listing comprises the major part of thedata containrd in the Sigma Center Storage and Retrieval System(SCfSRS) to date. (S. F. L.)

.-. .3i 736 (NAA-sR:l1980(voL4)) COMPILATION, EVALUA-TION, AND REDUCTION OF NEUTRON DIFFERENTIALSCATTERING DATA. Campbell, R. W.; Davis, S. K.; Alter,H.: Dunford, C. L., Berlarrd, R.. F. (Atomlcs Ir,ternat[onal,Canoga Park, Cal If.). Apr. 3, 1967. Contract AT[04-3)-701. 288P. Dep. CFST1.

A compilation Is gtven of the aq.pdar distributions of elasticallyacattere.d neutrons, based on avallahle experimental data, for iso-topes in the mass range 2 s A s 244. These data were analyzedand reduced into a form converr@t for use in digital computer cal-culations. The elastic differential acatterlng data are representedby expansions in a finite seriee of Legendre polynomials withenergy-dependent coefficients in the center-of-mass coordinatesystem. A listing of the Legendre coefficients for all angular dia -tritwtions, as well es plots of selectwt data, are includwi. The pri-mary source of experimental data was report BNL-400, secondedition. (S. F. L.)

1009 (ftNlAMt5j - ACTIVITIES OF’ THE CROSS-sECTION COMPILATION AND EVALUATION CENTENSAT THE BR~HfAvEN NATIONAL @%B(kiTOltY.Chcrnick, Jack (Brookhnvetr National Lab., Upton, N. i’.).[1966j. Contract AT(30-2)~Gen-16, 7p. (CONF-661014-2), f.kp. mn.’ C FS’f’f $1.00 CY, $0.50 mn.

5iiT10N COMPILATION cENTER SCISRS NEWSLETTER. .PART A. REFERENCE AND BfEfLIOGRAPHY. (Brookbaven .National Lab., Upton, N. Y.). June 196’f. 139P. DeP. c~s~. Frum fAfiA Conference on Nuclear Data, Pad% Frumw

A listing by reference of the Rterature incorporated into the “SCISRS bibliographic system ie presented together with a blbllo- :

A summary of activities in the compilation and evaluh -tlon of neutron cross sections is presented. (D, C. W.)

kraohic index that ie iisted by accemion number (reference ah- ; -.~re~latlon.) (D. C. W.) : .’

41

1967

i1989 (NY~?2-107) CINDA: AN IfiiEX fO ME LITERA-TURE ON MICROSCOPIC NEUTRON DATA., (Cohsmbia Univ.,New York. ENEA Neutron Data C~mpI!ation Ctmtre, Gif-snsr-Yvette (France)). July 1, 1966. Contract AT-30 -1-GEN-72. ,136P. (EANDC-60(U); CCDN-CI-1 1). DTI Extension.

A cumulative bibliography is given of the literature on micro-scopic neutron cross sections and allied data. Thc material isarranged in order of the target nucleus and by the type of data ‘rcfcrcnccd. CmTragc Is generally limited to scattering andrrac’tions induced by neutrons of energy <20 MeV, for epebific

‘elements and isotopes. information on (y On)and (y,f) ruactlonshas been {ncludcd for cmcs ISIwhich the y-ray energy IS icesthan NIS MeV and the (y,n) cross pectiqn greater than 0.1 mb.While most of the rcfercncee, covcrcd report on mdamsrcmcrtts,CINDA also Irscludcs fhrorctlcal calculatlone, cross eection

“evaluations, and compilations fpaofiar as they refer to epcciflctarget nuclel. (S. F. L.) ,.. . .“

35546 (ANLAS20, PP S-14) STATUS OF f3ASlC-NUtLEiRD.4T.\ REQUfREf) FOR FAST BREEDER REACTOR DEVEL42P-MENT. Cox, S. A. (Argonne National Lab., Ill.).

The present preckilon and availability of nuclear data are die-cussed. Fissien cross eectlona are examined in the light of recent2~tu measurement at AOW.R.E., Aldermas~n. s~ce the z~~wf{~sbncross section is used as a normalization standard for many crosa-section measurements, its statue 1s examioed in detail. The nor-mal izatien of neutron cspture crose .vectimse depends not ordy on tiethe I%J fission cross section, tryt also on the 10B(n, a) cross sectionsod measurements of s@erlcsd ehell transmission. Each normal-ization procedure is discussed in detaii. ft is concluded that muchof the existing dlapartty in reaulta for fission end capture croesscctlona would be greatly reduced by a critical renormalization ofali of 2he data to currently acceptable valuee of the 23SUfissioncross section and the 10B(rs,a) cross section. Recent re-evaluationsof measurements of spherical shell trmsmisaion also tend to re-duce the disparity. Neutron scattering cross sections from 0.3- ‘1.5 3feV are in good shape. Because of the recent observation oftntermcdiate structure 10 elastic neutron-scattering cross sections,measurements must be made in great detaU especially beiow‘3-5 hfeV. More data are needed from 1.5-5 hfeV. Above 5 MeVthe optical model can be ueed to interpolate between measurementsrather wideIy epaced in energy. Recent U measurements confirmthe nonlinearity of U va En and alao suggest the preeence of enanomaly at -0.4 .MeV. Requests for nuclear data are exsmtrsed ac-cording to the feasibility of the measurement end the man-year re-quirement necessary to achieve the requested precision. A list of31 references is bscluded. (authi

21526 INELASTIC SCATTERf~G MEASUREMENTS IN A - . .FAST REACTOR BY THE SPHERICAL SHELL METHOD, Davsryi :WIlllam G.; Amundson, Paul 1. (Argonne National Lab., 111.). ,Nucl. Scl. Ersg., 26:, lxl-23(Apr. 1967). .,

The spherical ehefi method for Investigating tnelaatt’c scatter’- ‘ing cross sections was used in a fact-reactor. core environment. ‘The chdnges In 2E.U73SU, 226u735u, ~d 2Muf135u fission ratioscaueed by placing shells of graphtie, sodium, alurnlnum, ion,stalnlcee ktecl, Iesdl add depleted uranium around the fission .“chambers were measured, The etudled show that reasonsldyaccurate measurements can be md,e ,12sa fast-reactor core.When comparison can be made, our results are In exceltentsgreementwith the fission spectrum results of Bethe, Beyster, Iand Carter. Comparisons of the experimental data with values Icalculated using two multlgroup crose -sectton setl show clearly 1,

‘ where these date sets are accurate and where they are {n error.(auth)

,. ..

Neutron Cross Sections:1. Sources of Data

h1932 (TfD-233i7(Sujspl:i)) CtiA: ‘AN INDEX TO THELITERATURE ON Microscopic NEUTRON DATA. ftllvlaloss

‘of Technical Information Extension (AEC), Oak Ridge, Tern.ENEA Neutron Oats Cornptlatfoo Centre, Gtf-sur-Yvette (Frances)).

.

Oct. 15, 1966. 327p. (EANDC-66(U); CCDN-CI-13). Dep. mn.CFSTI $3.00 cy, $0.65 mu.

A compilation of all the additions enterbd into tha CINDA master:library tape between July 1, 1966 and Oct. 15, 1966 ia prwwttcd.

.

Corrcctiosrs and improvements to prevfoua entries are Included.(D. C.W.)

. . .

23S41 ‘ (Nti-8R-Me~o-~231d) EViLfJAT’iON OF HEik.EVEN-EVQN fIRJCtiE ELASTIC AND fNEfASTIC CROSS SEC-

TIONS BY blEANS dF A NONSPHERICAL OPTICAL MOLSEL.DurdOrd, ch~rles L. IAtomica international, Canoga Purk,Callf.). Mur. 15i.lf167. ContrucL AT(04-3)-701. 23p. Dep. :mn. CFSTf $3.00 cy, $0.65 mn.

The hea%y even-even Isotopes were Irsveirtigatcd with a comidncdnensf.dwricaf pulesslkd upucaf mudel and Wmpwmd-nucleurn theory.C.ompound-nuulcua the~ry provldtiti a mcshod for trwtttng all therfxiction croea sections [fission, capture, (ss,0’), (n,2nJt. An anal -yaia of 2SW and ‘STb for which considerable data la awsllalde hasjustified the uaefutness of this approach to evaluation. The non-ephericat optical model per~ite the evaluator to scpamtc the clas-ttc and frrelaatic components of a measured angular dlatriisutionfor these isotopes, Combined with an appropriate compoynd-nucleue model, it 1s possible to riifferenttate betwocn cortfllctbsg

. seta of 2%5 capture data withlp Use range of 10 to 100 keV. (outh). .

.(EANDC(E)-76(U)) NUCLEAR DATA RESEARCH fN

i~~lmTOM COMMUNITY. Progress Report, January 1-@cember 31, 1966. (Europears-Americsn Nuclear. Data Com-

mittee). Jan. 1967. 203p. Dep. . ‘. . -..

. . .

NEUT~ONS, FAST -reactions (n,f) ~fth phi20nlti-239 sod”-240 at 5 to 150 keV, cross eectloos for (E)

URANRJM-235 —neutron fiadion cross aectlon at 30 and 64keV (E)

NEUTRONS, FAST-reactfons (n,tl with uranium-235 ●t 30and 64 kcV, crose sections for (E)------ . . . . ,-, , .- .--,.

..0

NEUTRONS, ‘FAST —reactions (n,t) with u~anium-235 at 7 to14 MeV, neutron emieslon in (E)

URANfUM-235 —neutron fission at 7 to 14 MeV, neutron emis-sion tn (E) .

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1967

3s610 (ANL7i120, Pp 80-7) EVALUATION OF BASICCROSS-SECTIONDATA BY ANALYSISOF FAST CRITICALASSEMBLIES. Filb’nore, F. L.; Sp’edht, E. R.; Vernon, A. R.;Ottewitte, E. H. (Atomlce Intematiodal, Canog~ Park, Calif.).~ Calculation of the propertlea of a number of fast crltlcal aa-aemhl ies are being carried out as part of a CantintIing Pr05r~ fortesting and evaluating multlgroup cross sections for fast dalcula-tions. The experiments included In the present analysis have beenchosen to cover a wide range of fiiel materiala and reaotor apcc-tra. Tbln fncressea the ability to Idcnttfy errors according to thematerial and energy range br which they occur. The assembliesstudied include a number of 2%J-fueled ZPR-111 assemblies;ZPR-UI-45 and 45A, driven Pu assembllee which wc!rc muinly usedfor Doppler measurements; the SEFOR mockup, ZPR-fli”-47; the “Pu-fueled asaembly, ZPR-111-48; ZEBRA Core 5; the smali fast ,

‘ esaemblies POPSY sod JEZEBEL (fueled with metallic P@. andGODIVA Uueled with metallic U). The properties examined in-clude critical mass, Dnppler effect, fission ratioa, end the reac-tivity worthe of varloua material replacement. Thp propertiesof tbe small fast aasemblles depend only on the high-energy data;they are practicality independent of cxo8a sections below 100 keV.However, the larger aaeembliea reqiire nccuratc data down toabeut 100 eV. Aii of the multigroup cross sections have been con-structed using basic microscopic cross-aectimr data and have notbeen sdjuated to force agreement with the critlcai-asaembly, data.For the large, rnoft-spectrum asaembliea, the croaa sections wereweighted by a fine-group apcwtrum calculated for, each aaaembly.,A Mat of 25 references la tncluded. (auth) I

21536 THE M’EASUiEMENT OF 239Pu CAPTUR”E T~ FISSfONRATIOS IN FAST REACTOR LATTICES. FOX, W. N.; ikbmond,R.; Skillings, D. J.; Wheeler, R. C. (Atomic Energy F-stabiieh-ment, Winfritb, Eng.). J. Brit. Nucl. Energy Sot., 6: 63-79 (Jan.1967),

The breeding gain of plutonlum fuelled faat reactors Ia’stronglyInfluenced by the capture-to-fission fatio at of 23sPu. In the softerspectra associated with a large dilute fact reactor, the uncertaintyin at IS of the order of ●25%. TO reduce ibis ~cerminty. two newtechniques are being developed for use in zero-energy fast reactorlattices. in the first methud, measurements arc made in a latticewhich is arranged to have an infinite mulupiwauun constant h nearto unity, so that k. can be determined by a null reactivity techniquewltbout introducing significant, sysiema}ic errors. All the impertatitneutron fission and capture rates, except for the capture rate inZ31PU, are then measured in \hls modif~ed lattice; and as is i~errcd’frnm the known neutron baiancc. The second method, which is at anearlier stage of development than the first, involves the direct ob-servation of capture end fission y rays from a 23tPu sample placed

oin a neutron beam @ken from the zero-energy fast reactor core. Acoincidence technique la used to distinguish between capture andfission y rays, and the apparatus is calibrated by repeating themeasurement in’s tbcrmal neutron beam fer which u, is known.Some preliminary results obtained by the flret technique indicatethat current nuclear data sets underestimate at significantly indilute fast reactor lattices. (autb)

Neutron Cross Sections:1. Sources of Data

;3536 (JAERI-1126)PROCEEDINGS OF THi 2NrisEii- ~INAR ON FAST-NEUTRON CROSS SECTIONS [Hii LD IN TOKYO,18-20 AUGUST 1966]. [Jcpan Atomic Energy Rcstmrch Inst.,Tokyo). Aug. 1968. i 16P. (In Japanese). (CONF-660928).Dep. mn.

Thn 2nd Seminar on Fast-NeutroryCro.ss Sections was held at theTokai Research Establishment of the Japan Atomic Energy Re-search institute on 18 –20 August, 1966. Ahout 70 scientists in thefields of the nuciear and reactor physics partlclpatcd. The maintopics were optical-model analyses, resbnsnce analyses, and prob-lems on fission cross scctlons. Some otlglnsl papers presented atthis Seminar, In addition, tcr review papers on the shove topics, ●recontalncd In this Proceedings. (auth)

-.——33854 (rii-ii~lj“&FiA cOMPuT~~ PIIOGRAMF~fiCALCULATION OF NEUTRON SPECTRA AND AVERAGE CtiOSgSECTIONS INTHE HIGH ENERGY REGION. Mathe~s. D. R.;Archibnld, R. J. (General Dynamics Corp., San Dl~’go, Calif.Generai Atomic DIv.)., Jan. 20s 1967. Contract ATt04-3)-167075p. Dep. CFSTL

A computer program, flAF, waa wri~t~n tO ~OnWute neutrOnftuxcs and cur,rcnts froth the B, oquatlons for n rn~xilllum 011’740 energy groups above tbe thermal energy region. Th{: cai-cul;tted fluxes mtiy bc used to prcy~re avt!ruge truss sc~ lionsfor up to 99 Lrou[i energy groups. Special dam bundling lcch -niqucs arc used tn UIIOWthe practical utiilmitiori of suc,h .i Lirb!enumber of cnurgy groups. The prugrwrr IS writt~’n In lhcFtjRTIiAN-lV lsnguuge for tho UNIVAC- 110I3 compulc+r. {.ulth)

25518 (WAsH-1071)” THE AEC NUC.LEAR CROSS SECTIONSADVISORY GROUP MEETING AT ARGONNE, ILLfNOIS, NOVEM- ‘BER 10-11, 1966. Motz, H. T. (comp.) (Los Alamos ScientificLab., N. Mex.). Contract W-7405 -eog-36. 234P. (EANDC(llS)- ●

91-U; R4DC(US)-5-U). Dep. mn. CFSTI $3.00 CY, $0.65 mn.The statua of activities in the crotis-sect’ion measurement pro-

grartr is summarized., Prclfminary ~sta sre included.. (D. C. W.) -

42780” ‘SOMEPROBLEMS FOR THE PROiWCTION OF RE-ACTOR CONSTANTS. Nip~n ‘Genshiryoku Gskkaishi, 9: 386-95(July 1967). (In Japa~ese).

An evaluation of available cross section data IS given. The useof computer cod?s for gmeratlon of cross section libraries to beused with reactor calculations is [ii&cussed; tbe cross scct[on ac-curacy, aa calculated by these computer probmnms, Is discussed.(M.’L.S.)

.

33958 (BN&325(2nd Ed.) (Suppl.2)(Vol.2C)) NEUTRON CtiSSSECTIONS. VOL~E ffC. Z equals 61”TO 87. Goldberg,Murrey D.; Mughabghab, Satd F.: Purohiti Suqmdra N.: Msgurno,Benjsmfn A.: May, Victoria A. (Brookhayen Natfona~ Lab., Up-N. Y.). Aug. 1966, 439p. Dep. CFSTI.

An updated compilation of neutron cross sectfens and reseosnemparameters 1s presented for 2,= 61 to 67 nuclei. The referencesources for the data are rtlao listed. (D. C.W’.)

43

19673WT’– (ANL-7320, Op 27.S0) THE AIJTOMi?ELiPR}.PARA-TION,OFMU LTIGROII? CROSS SfiCTK)N9 FOR FAST R1:ACTCJR ‘ANALYSIS USR$U THE MC2 CODE. O’shen, D. M. (combustionEnglnccrlng, Inc., Windsor, Comf. );TOPPC1, B. J.; RafKh A. II.(Armmnc Nntlonnl Lnb., Ill.).

Tie fully nutomnted mt!ltl~rmp-cross-scctl(]n prcfmrntlon pro-grnm hiC2 mnken usc of nn tvn!unt~l nuclenr (Infn file (~;NrIF) asIts bmik’ in~t. The riogr, e 1{,uhl[ h the lNI)F data In Inltlally sub-dlvkfcrl prcparntory to nvcrnglng Is varlohlc In MC*. Cross SCC- .tion.v in the rcmlvcd rcamroncc rcglon arc calculotcd through useof Dc@er-broadened Ilne shapes and include etfccts duc to lnter-fcrrncc scattering end the Influence of ovcrlapp[ng rcsbnancea Invnrloun lsotnpm In the’ mixture. Unresolved resonance cross nec-tlone nre obtahred by mmn~ of averngca over fluittiie ,?O~cr-Thomnfi dlstrlbutiona of the neutron and ftaaion widths. Quantlticswhich nrc smoothly vnrying with respect te energy arc representedh tire library by coordinates of cnd points of lincat’ segments takenfrom In E vs In u, In E vo u, or E vs u graphs. fnelaatlc scatteringnnd n,2k matrices are computed from excitation foncliona for indi-vidual levels and by use of a nuclear evaporation model abov:’theresnlved rcglon. E1aatic-scattcrtng cross sectioms are computedfrom Legcndre cocfficienta for the expansions of the angular dis- ‘triirution data for scattering. A fundamental-mede-weigbtlng spec- itrum for the problcm som~altion may be obtained for either the “P1 or tho consistent Ifl or PI approximations. Rer4tlon on bucklingto criticality is optional. The generated spcct~ is uasd to con-tract the fine-group croea. ecctlona to a spwUied set of broad-group multigroup cross sections. (autb)

..- .-3iq66 (PAEC(A)IN46U REAcToR c~oss =cTi@=.A Literature Search; (Philippine Atotnlo Energy Commia!iion,Manila). NOV. 1966. 131P. Dep. ,

A bibliography of 805 entries ie presented on nuclear reactioncross. aectiona. The refcrcncea cited ,wem abstracted in NuclearScience Abtitrttcta during tbe periud $icijlembcr 8, 1948, to October1965. (S. F.L.)”

35383 (ANL-’732O,Pfl47-53) PRESENTATION OF THEMU LTIGROUP CROSS-SECTION SET PREPARED AT CADA-RACHE. Ravier, J.; ChaUrnont, J. M. (Commiaeariat a i’En-ergie Atotnique, Cadamche (France). Centre d’Etudes Nu-clealres).

A aet of multigr&p cross aectiotis has been developed atCadnrachc. After a short review of the aourcea of baaic nucleardata. the report explaina how the multigroup aet was developedand how it ia currently ueed; then a brief comparison betweenexperimental and calculated reaulta ia given. A Ilet of 22 ref-crencoa la fnqluded. (auth) ‘

33853 (EANIIC(E)-78W)) lNT1tOfXfCTIO’~-TO KFK ‘i~u“NEUTRON CROSS SECTIONS FOR FAST REACTOR MArEiil-ALS.” PART 1. “EVALUATION. ” sch~i(it , J. J. (Kerniur-achungazentrum, Karlaruhe (West Got-many), fnst itut fuer Neu-troncnpbyaik und Reaktortechnlk). Mar.. 19fi7. i~P. DeP.

The neutron data eveluution that bus been vc rfurmed M Karls-ruhe ainco tbe beginnlog of the fast breeder i.eacior project in19iI0 is outiincd. (D. C.\V.) “

,.

46683 (AN&7325, pp 197-200) NUCLEAR CONSTANTS.Stufwgia, D. C.; Tevebaugh, A. D.; Blngie, J. D. (Argonne Na-tiormi Lab.. IiI. ).

L)cvclopmrnia arc :cpnricd for studica nn: neutron capiureCross sections of rcacior, structural, and controi mnicrinle:and capiurc-to-fission croea-acction rBtioa of fiaaiic and fertileapccles. (P, C,}i. )

-..

Neutron Cross Sections:1968 1. Sources of Data27086 (ANL-7375, w 176-7) ~CLEAR CONSTANTS.(Argonne Nationaf Lab., Ill.).

PreIlminary resultn in tbe program to mea6ure ,capture cmsosectione,for fast reactor materiais and to meaaure and calcufatocapture-to-f laeion ratios for lJSPtt, 24ePU, 2UPII, ~SU, ‘SJU, and~S.u in EBR-ll ae a fumt{on of peition are reported. tD.C.W.)

53165 (ANL-7425, PP 190-2) NUCLEAR CONSFANTS.(Argonne Nati9nW Lab., Iii.).

current progress 1s reported for neutrar capture croes scctfmwof reactor materiale, capture-to-finsirxr, c~oaa-scciinn ratioe dfiaaile and fertiie materiaie irradiated in Ef3ft-11, and preliminaryinvee tigatfone of trltium yiekfe produced in ,faat qcut ron f iasinn.(D.c.w.) , ,

li515 THE Lf.S. EXPERIMENTAL PROGRAbitiE FOR F~fiTftEACTOR PHYSICS. Averyi R.; D[ckerman, C. E.; hnto, W. Y.jMng, J, K.: Smith, A. B. (Argonne Nationsl Lab.. XII.). pp 403-zo of Fact Breeder Reactors. Evane, P. V.(d.). Oaford, Per-pmon Press, 1967.

From Britleh Nuclear Ene&y Society Conference on FactBreeder Reactora, LOndOn. see CONF-660502.

I pmgreae in basic cross-section meaeuremcnte in ihe reeonatrce,intcrmcdiaie, and continuum regions la described. Criticaf experi-ments discuescd relate to Doppler effects, Na void effecte, ●ndtoned com etudiea. Other test pmgrammes reviewed include tire ‘SEFORproject, ~d the ~t-of-pfle and TREAT Pperimenta related10safety. (fJK) .

?’ .

~4i414 (GA-6773) INTEGRAL tiEUTRON THERMALIZA-TION. Quarterly Progress Report for the Period Ending June 30,1968. Beyster, J. R,; Borgonovi, G. M,; Houston, D. H.; Koppei,J. U.; SIaggte, E. L.: Sprevak, D.; Young, J. A, (Gulf GeneralAtomic, Inc., San Diego, Calif.). July 10, 1968. Contract AT-(04-3)-167. SOP. Dep. CFSTI.

A number of tbcoreticai aiudies completed during tbie pericdare discussed. The final conclusions reaultlng from the firatprincipiee calculation for beryliium are summarized. A theorati-caf scattering iaw for U02 waa compietcd; however, some addi-tional numerical .studica remain io be done bcfom this work canbe incorporated in the ENDF. A ncw modci for polyethylene is

I also described, and comparisons between reeuitn of lhie Modelad experiment are preeented. The lattice dynamicai model forberyliium oxide waa uacd to caiculate a frequency apcctrum anda c.caticring law in tho incoherent approximation. A calctdaied

( total crosfi section for BeO, inciuding coherent ciaatic scattoriW,is preacntcd ae part of tide. work. Some recently completed workon multiple scattering in dcable differential experiments io alaodescribed. This work relatea to probiema involved in the uae ofspecially rxmatructaf campleo designed 40 reduce muliipla acat-

iicring. Rcportn on work [n progmne include an cut] Inc of effortsbeing mado to improve cnpnhilitics for computing colwrcnt in-clastlc scaticring. Alno some preliminary work ie rq-mrtcrf con-cerning efforts to broaden significantly the acopc of the theoreti-cal annlyace underlying ENDF scattering laws by rcialing thetcmpe raturc dcpendmrce of the frcqucncy spcct ra to anha rmonlceffects. A report of the UC2 iotai cross section cxpcrimcnt nndtho nnaiyaia O( tho data conaiitutes the section on cxpcrimtmtalaludice. (nuth)

44

.

1968 “352S5 (AERE-PR/NW13) NUCLEAR PHYSICS DIVISIONPRCGREW REPORT FOR THE PERIOD MAY l-OCTOI_ifiR 31,1967. Colemnn, C. F. (cd.) (Atomic Energy Research Estnb-llshmcnt, I{arwell (England)). Feb. 1966. 69P. Dep. C FSTLUK.

Resenrch dealing wltb nuclear datx for renctom, nuclear strm-ture and dynamicn, radiatton detectors, accelerator technology,Moessbmter applloatfons, and ●strophysics ia summarized.(D.C.W.)

46698 (TID-24469) CINDA 68: AN INDEX TO THE UTERA- ‘TL’RE ON MICROSCOPIC NEUTRON DATA. (Division of Tec!mt-cal Information Extension (AEC), Oak flldge, TeM. Gosudarat-vennyl Komltet PO Ispol’zovantyu Atomnol Energtl SSSR, Obntmek,FizIko-EnergetIcheakll Inatitut. ENEA Neutron Data CompilationCentre, GIf-Sur-Yvette (France). Intrnrnational Atomic EnergyAgency, Vienna (Auatrlh). Nuclear Data Untt). June 1968. 1026p.DTIE Free.

A blbllographlc guida to experimental and theoratlcal lnforma-tton on neutron croaa sectlouso resonance parameters, thermal

ecattcrhtg laws; fle~ion parameters, and other related quanti - ‘tics la presented. A one-line format Includes the element, lso-topc, or compeund studied; the quantity studied; the typ of In- I Ivestigotiom, the type of reference; the Incident neutron energyrange; the complete reference for the document; the laboratoryat which the work waa performed; and brief comments on themetheds used and the reeulta obtained In the investigation. (D. C.W.)

Neutron Cross Sections:

1. Sources of Data..3738 NU~EEAll RE”ACTIONS. ‘Leonard, B. R. Jr. (13at-telle-Northwest, Rlcbiand, Wash.). pp 9-30 of Plutonium Hund-bnok. A Guide to the Technology. Vol. I. wick, 0. J. (cd,).New York, Gordon and Breach Science Pubiishera, 1967. ,

Tbe more Important fpaturee of neutron-Induced reactionn “fthe Pu isotopes are presented, with references to tabulations ofdetaiied data. (S. F. L.) ,

.-

20578 (WA$I!-1079) REPORTS TO “Tik AEC NUCLE”A.RCROSS SECTiONS ADVISORY COMMITTEE. , Meeting ,held atldnho Falls, Idnho, October 17-16, 1967. Moore, M. S. (cotnp.)(ldnho Nuclear Corp., Idaho FalleJ. Zo9P. (EANDc(us)-lo4-u$INDC(US)–2-U). Dcm CFSTI.

Progrcsp in’nume~ous Invest! jratione of neutron reactlona and,~hnrgcd-pnrtlcic reactions is summarized. information, in VaI_Yb8

; degrees of compietencae, la given qn cross eectiona, resonancapammetcrs, and level schemes. Some developrnenta b! bratru-mentation are alao outline+ (D.C.WJ ‘ a.

39627 (BN&50082, pp 19-24) NATIONAL NEUTRONCROSS SECTION CENTER, Pearlatein, S. (Brookhsven National Lab., Upton; N. Y.).

The activities of the center are summarized. Recommendedvaluea of the thermal neutron capture and fission croee sectionsand reeonance integrals of 2UAm, 21DBk,2~°Cf, 2$lCf, 252Cf, 2~~Cf,I$tcf, 2Ucm. 2~5cm. l~~cm. z~fcm. 2~8Cm. and 2UPU. which arebased on a syet-ematlc treatment&f avatiable da~a~.are pre_&~ted.The random matrix theorv of nuclesr cross-section fluctuations

32422 (CCDN-NW-7) NEWSLETTER NO. 7. (ENEA Neu- s was extended to include tie pneeihili~ of time reversal vioiatiantron Data Compilation Cmtre, Gif-sur-Yvetk (France)). Mar.

In nuclear forces. Qticat-model parameters that provide a gead1968. 73D. L~en. flt to tbe crose sectlona of 2t4Pb. 20~Pb. and ZOaPbat 1 MeV were.-

A IIsting of the neutron cross-section evaIwntlom that werenvaRable from CCDN in March, 1968, ie prcseht~. (D. C. W.)

37340 (EANDC (E)-89U) PROORESS REPORT ON NUCLEARDATA RE5EARCH IN THE EURATOM cOMMIJNITY, JANUARY I-DEeEMBER 31, 1967. (European-American Nuclear Data COm-mittee. Euro~an-Arnerican Committee on Reactor Physics).Feb. 1968. 239p. Dep.

Research activities and programe in the EURATOM communityduring the period Jan. 1 to Dec. 31, 1967, are summarized. Neu-tron. croae section meatmrement programe compriee the bulk ofthe material included. (D. C.WJ

.,

18078 ‘(&[email protected])) NIJC LE”AR DATA F(JR REA(J-TORS. Preceedinge Series. Proceedings bf a Conference heldin Paris, 17-21 ~tober 1966. (International Atomic Energy~ncy, Vlema (Austria)). 1967. 569p. (CONXJ-661014-(VOL , >

IAEA: $ 12.00; Austrian Schilltngs 310, -; $ 4.4.8; F Fr 58ti8L);Dh; 46,-. ,.

Separate abstracts were prepared for 23 of the 67 papere bt-eluded. Thirteen papers” are included in abstract form only. Thentber 31 papera have previously appeared to NSA and may belocated by referring to CONF-661OI4 in the report number index.(D.C. W.)

.,,. !.For abstracts oj individual pnpevs see: 18099–18105, 18146, ,

18147, 18192–18195, 18281-18289, and 18347.

. . .. —––— -------— --obtained. Reeonance parameter for 46 resonances of Ho below?35 eV were used in fitUng total cross sectian data on Ho to aBreit-Wigner multilevel scattering and slngie-levei sbeorptianformula. (D. C. W.)

18194 MICROSCOPIC NE-~fiON SCATTERING “CROSSSECTIONS FOR REACTOR DESIGN. Smiih, A. B.; Lister, D.(Argnnnc National Lab., 111.). pp 399-408 of Nuclear Data fnrReactors. Vienna, Intematlnnal Atomic Energy Agency, 1967.

Fram IAEA Conference on Nuclear Data, Paris. S@eSTI/PuB-140fVol.l); CONF-66101&(V01 .1).

TIW results ohtaincrf frnm a comprehensive experimental studyof elantic and Inrlastlc neutron scattering arc reported The inei -dcnt neutron energy Interval was 0.3 to 1.5 MeV and scattcri~fqom 50 elements extending from Be. to U was invef!tlgatml. Faatneutron time-o[-ftlght techniques including a muiti-atigl~ detectorsystem and fully automated computer controi were ut iii?.cd toachieve a gond ncatlercd neutron reaoiutlon. Differential eiastlcand inelaetlc ecaltering croea aectione were determ irtcd at eightor more anglea at incident neutron energy ’lntervaln c.f 50’keV orleas. The elaatlc anguiar dlstributlona are expressed ae Legendreexpansiorw of up to six terms. The observed differential ineiastlccrotie - arctions arc” tntcgrated to obtain the respective inelasticexcitation cross-sections. The experimental reeulte are commredwith opt ical-modei Haiiser- Feshbach eaiculations; and it iq abawmthat intcrpoiatlona of experimental valnes, beeed on the rn~el, arevalid. Experimental evidence for intermediate resonance structure,width fluctuation effects, and nuciear deformation Is presented.The Ioftuencc of each on calculation ia illustrated. (autb)

1968

20576 (ORNL-TM-2159) SOME RECENT NUCLEAR CROS9 “SECTION MEASUREMENTS AT ORNL, OCTOBER 1, 1967-FEBRUARY 29, 1968. Stelsono P. H. (Oak Ridge National Lab., !Term.). Mar. 1968. Contract W-’f4O5-eng-26. 20p. Dep. CFSTI:

Some recent measurements of differential cmsa sections mxf “Y apcctra for the reactlooe l~N(n,n’)}4N, 1{N(n,p)*4C, and 14N(n,u)11B, Ithe neutron tot.d cross aectlon of ‘O; y spectra from reaotranceand thermal neutron ca lure by ‘40Ce, 3tK, ‘lK, ‘05Re, lnRe, 201Tl, :f20*T1,l12sn, ll~sn, mrj f ‘Sri; and capture and flefIiOU Croaa section.sfor z~spu from thermal to 30 keV and for ‘SU from thermal to 1 aVare aumnrartzed, Calculations of the elaatic and lnelaatic scatter-ing cmse sections for ‘Fe am also reported, aa is the afatus ofthe electron linear accelerato~. (D. O. W.). . .

3534? BASIC NUCLEAR D“ATA FOSi’THE HIG”HER PLUTO-NIUM ISOTOPES. Ylftah, S.; Scbrnidto J. J.; Caner, M.; Segev,’M. (Soreq Nuclear Research Certtre, Yavne, Israel). pp 123-49,of Frtat Reactor Phynlce. Vol. I. Vienna, Xnternatlonsl AtomicEnergy &ency, 1968.

From SympoBium on Feet Reactor Phyeico and Related Safety LProblbmx, Karlandie, Germany.’ See STI/PUB-165(VoLl):CONF~671043-(VOl.1).

Faat reactor fuel may have an appreciable centent of high Pu!aotopea, the amount varying adcording to the source. Therefore, .in calculation of stailc and dynamic reactor characteriatlcs, re-liable basic nuclear data are needed’not ordy for 2sSPu but for thehigher laotopce as well. Reactor cotnputationa depend on crosssections ae funrtlone of energj, dilution and tempemture. Basicnuclear data for a fuel ieotope contdeta therefore of aver~e cross ,ecctions turd reaonnnce parameter. Experiment alone does notfurnish ouch data in a final complete form. In fact, the eaperi-rnentel ittformation needs inte tp retation, weighting, evaluationnnd often nlso interpolation on thcoretlcrd grounds. Within theiramework of contrnclrd research with the Association EL’RATOM-Xnrlmuhc on fnai readorw, an Wnhmtlon WRS mndc O( txtslc nu-clrer data for the high Pu isotnpcs. Semc pertinent pnrts nndnspccte of thu wmluatlon are summarl cd. I{enonancc pnrsmctera

tnnd rrons ncctiona ●re presented for ; OPu, ‘tlpu, and ltl Pu In theform of oxperlmentai ●nd recommended daia, Completo sets ofpnram~tern include the first 43, 61, ●nd 20 remnnnccm of thesetnotopon, roepectlveiy. Average parameters am derlvcd fmmthrac sets, 10 be uncd ●l higher energlca where elthor the pnrx-motrlzatlon 16 tncomplcte or the resonances unreooived. Although

‘ the samples are, ●e ● role, too poor for a dlrec~ derivation of

●ati-tical distritmttone, there 1s eno@b general tmowiedge on the “subject tadxy to fix theme diatritmtiopa witbio oarrow llmite. hulk)

Neutron Cross Sections:.

1. Sources of Data-53379 MODERN.FAST REACTOf7 CROSS SECTION SYSTEMS.

Yiftah, S.; Segev, M.: Lemanska, M.; Caner, M. (Israel AtomicEnergy Commission, Yavne). pp fln9.1-8 of Proceedings of theInternational Conference on the Safety of Faat Reactors, Aix-en-Provence, September 19-22, 1967. Denielou, G. (cd.). Paria,

, Commiasariat a l“Energie Atomlque, 1967.See CONF-670916.Several clasaea of problems must he solved in the preparation

of a group cross section aet for fast rwtctor calculations. Thefirst step Is the evaluation of the baaic nuclear data, inclurflngcompilation of all available experimental information, calculations.baecd on nuclear modeia to fill gaps in the data, clarfficatimr ofInconsistencies and conflicting experimental information usingayatematics or comWting weighted averagca, in order to eatabllsha complete almoat point-wise scheme of the energy dependence ofcross aectlona and other nuclear data in the energy range of in-terest. The second class of problems reiates to the propct dcfl -nition of group cross acctiona. When using exietfng group croaasections or constructing new ones, onc must have a clear fdcawhat type of group prametera arc Involved and exactly how thtirdefinition aa averagea or integraia over prcducte of basio nucleardata and weighting functions are given. The third prcblem con-cerns the weighting funotione, which determine the group-averagingtedhnlque. Different group tabie types stem from different atruc-turea in the weighting functions, namely ihe gross ntmcturr, inter-mediate structure and fine structure. With the above conskiera-tlon In mind, three mcdern group croaa section aeta are compired.These are the Ruaalan 26-group set ABN, the Argonne 22-groupset ANL, and the recently conatxucted Iaraell 30-group set YSL.In the comparison, attention 1s pzId to group structure, type ofcross sections, repreaentatlon and magnitude of seLf-ahieldlogfactors and temperature-dependence. Some typlcaf faat reactorprublems are run with the ABN snd YSL aeta and the reeultacom pa red. (auth)

.

.

.

46


2. ENDF/B Tapes and Other Evaluated Lists

196723404 [ORNL-P-2914) NEUTRON CROSSSEiTiONSANDREACTION PRODUCTS FORH, C, N, ANDO FOR THE EtiERGYRANGE FROhITHERMAL TO15MeV. Auxler, J.A.: Brown,M. D. (Oak Ridge National hb., Term.). [1966]. Contract W.7405 -eng.26. 16P. (CONF-660920-15). Dep. mn. CFSTI $3.ooCY, $0.65 mn.

From 1st International Congress of the International Radiationprotection Assn., Rome, Italy.

The accurate calculation of neutron dose must be based on de-finitive cross sections and a precise knowledge of the reactionproducts in tissue. AIthough there are still several uncertaintiestm these parameters, a compilation has been made of the mostdetailed cross-section d,,ta available md reaction prO~”ctSforthe four major elements in tissue (i,e., H, C, N, and O). The com-pilation is for neutron energies below 15 MeV, but tie ener~ in-terval requiring the most stud.v and analysis was that from 2.5 to15 MeV. Particular attention was directed to the nonelastic re-actions [e.g., the C(n,nO) 3a reaction]. Average values for the en-ergies of the various charged particles as a function of tie energyof the Incident neutron have been computed. These values Werecompiled to provide a basis for, revision of the dose-distributionfunctions for neutron exposures of man and of ammals used ~radiobiological studies. An analysis of the results of various nsea-suremrmts are compared with calculated values based on thesecross sections and with the values listed in NBS Handbook 63.(auti)

338ff4 (l,A-3695) 6LI AND 7LI DATA IN Tl{ft fZNf_lF/ff. Ft)l{\l.\T I?attilt. M. E.: Dudr.htk, D. J.; I,afhUVO, R. d. (L.?q

A1.In.0~ $+irntific I.nh., N. h!cx. ). Mar. 1!367. Crmtracl W-7405- .c.ng-31i. .~9P. fh,P. CFST1.

At tht~ Cross Scctlon Evaluation Working Group (CSEWG) Meet-ing on .l~jno 9-10. 1966, at Rrookhavcn National Lnhoratory, theI.m Al:inws Sclcntiflc Lahorstory was ass”igncd the rcsponslbllityof pm pnring t h{. duta for the. isotopes 6LI and lLi for the fl mt vcr-SIOIIuf tho Evaluated Nuclear Data File/B (E NDF/B) tape. Thesedata wc re asscmhled in the ENDF/B format amd were sent to theCross sCCtlOn Evaluation Center (CSEC) at Ilrookhaven NationalLaboratory. Most of the data arc from the AWHE d~ta fllc orlgi-nafcd hy K. P~rkt!r of Aldcrnmston. Values for FMB and $, alongwith Lcgcwlrc cocfflcicnts for the elastic scattering angular dls-tril,utiuns, vwrc received from H. Alter of Atomlcs Intcrrmtiortal.PI(,I. !,( UN. ort~inal AN’I{K cross section data converted to theKXDI”;R ft!rmat arc prcscntcd. The ENDF/B listlngs for the ‘L1and 1Li datn, m they appeared on the first version (approximately ;Fchruar} 1967) of the fINDF/E3 tape, are shown. (auth)

35480 FISSION AND THE SYNTHE51S OF HEAVY N-U~L”EIBY RAPID NEUTRON CAPTURE. Bell, George 1. (Los Alamott.Sdentlflc Lab., N. hlex.). Contract W-7405 -e’~-36. phy~.Rev., 168: 1127 -41[June 20, 1967). (LA-DC-6513).

The role of flssIon 1s exsm!ned In the synthesis of heavy nucleiby multiple capture of neutrons In thermonuclear explosions. Evi-dence from the recent Tweed and Cyclamen experiment Indicatingthat neutron -hrduced fission is a eerio~s source c.f depletlon inneutron capture chalne which start from targets of 2i2Pu and 243Amis reviewed. An analysis of Tweed abundances js made to obtaincapture-to-fission ratios for the cxfd-A plutonium isotopes throughA = 253, The llquld-drop model of Myers and Swiatecki plus em-pirical shell correetione and pairfpg cnergles is then used in orderto correlate and predict spontaneous fission lifetimes and fissionbarriers. For nuclei having’ Z ~ 101 and ,N ~, 157, the shell cor-rection lS extrapoI:itcd, assuming it to be a function of N plus afunction of Z. Thus, neutron binding energies, fission barriers,and spontaneous fi~sion lifetimes for neutron-rich heavy nucleiare obtained. Capture-to -fission ratios are @mated for many of’these nu’clei, and qualitative agreement is found with laboratoryand Tweed results. . The extrapolation ia continued out to N = 159pnd Z = 104. It is concluded that by using the liquid-drop modelplus semiempirical shell corrections, one can obtain capture-to-fission ratios and spontaneous fission half-lives which are usefullyaccurate. However, for predicting properties of nuclei having Z >

, 104, N Z 159, one needs, in this formalism, an accurate way ofpredicting ehell corrections or nuclear spa?ses. (auth)

25sil ( 1~-Dc_s640) 2$3UCROSS ‘S~CTk3f& A’s DETER-MINED USING NEUTRONS FROM A NUCLEAR DETONATION.flcrgcn, D. W. (L08 Alamos Scientific Lab., N. Mex.). [1966].Ctintrsct W-7405 -eng-36. 5p. (CONF-670602-1). Dep. CFSTI.

From 13th Amtual Meethuz of the American Nuclear Society,San Diego, CalIf.

Sore@ mcasurem,onts of the capture and fiselon cross aectionaof 233Uin which tarert foils were exnosed to a moderated flux from-.a huclear exploslon are Wtmmarlzed. Relation fission cross scc -

,tions are presented for enctgles of 20 to IOCeV, as well as infor-mation on the capture-to-fission ratio between 27 and 63 ev. Theresults of resonance analyees using both sin le-lebel and mu”lti-

5lev~l formalisms Indicate that the fission of 33Utakes placethrough eeveral channels, (D. C. W.)

47

1967

27568 (LA-3676) THE ‘~sU ~ISSION AND $3A@TURE CR095~ECTIONS AND THEIR ANALYSIS AT LOW ENERGIES. Bergen,Delmar W. (Lms Alamos Scimttlfic Lab., N. Mex.). Dec. 1966.f$ontract W-7405 -eng-36. 76p. Dep. CFSTI.

Thesis. Submitted to Univ. of New Mexico [Albuquerque].The 2NU fission and capture crbss sections were meaeured :

ualng a nuclear-device neutron source and time-of-flight tech- Iniques. Cross section data are presented from 20 to I,& eV forfission and from 20 to 63 eV for fission + daphtr,e. .Tbe resonance ;region (20 eV to G3 eV) was fitted with Imth a single-level function ~consisting of a sum of Breit-Wlgner levels and the Reich andMoore multilevel function based on R-matrix theory. The result-ing resonance parameters are listed and discussed. In order to ,establish the validity of the resonance parameters detived fromthe multilevel fit, a study is presented of the cross section de,rlvedfrom two and three hypothetical resonances under various condi-tions and of the cross sections obtained from randomly generated ‘rcaonancea. (auth) .

3B306 URANI M-233 CROSS SECTIONS AS”DETERkllNEDJUS NQ NEUTRON FROM A NUCLEAR DETONATION. Bergen,

/D W. (LOS Alamos Scien(lfic hb., N. Mex.). Trans. Amer. ‘Nucl. Soo., 10: 221 (June 1967).

From 13th Annual Mocttng of the Amertcan Nuclear %clety,‘&n Dle~, Calif., June 11-15, 1967. see GONF-670602.

27579 (UNC-5099) NEUTRON CROSS SECTfr3NS OF l%J,...2M~;, 2371f,~~~fJ,2J4u, 2~u, 233pu, 240~, w, Pb, Nl, Cr, c, tL[o 7f&

AND T. BertIn, M. C.; Celnlk, J.: Flesher, H.; GrochowekI, G.;Kalo9, M. H.; Ray, J. H.; Troubetzkoy, E. S. (United Nuclear iCorp., white Plains, N. Y. Development Div.). Dec. 31, 1!364.Contract DA-18 -108 -AMC-131(A). 292p. (AD-616629).

Neutron cr,oss-section sets were prepared for 16 elements orlsotopcs fnr neutron energies from 0.037 eV to 18 MeV. The crosatscctiona tabulated Include the total, elastic, inelazzifc, (n,2n) andfiseion cross sections, as weil aa cross secifons for charged-particle emission. information is also given on the angular dis-tribution of elastically scattered neutrons end on the energy dis-tribution of neutrons and y rays following nonelastic scattering.(aytfr)

Neutron Cross Sections;

2. END.F/B Tapes ...

‘ 38307 \ EVALUATION OF 22SUCROSS’SECTfONS. Drake,M. K. (Oeneral Atomic Div., General Dynsmtcs Corp., 91n

‘ Dfego, CalIf.). Trans. Amer. Nucl. SOO., 10: 221-2 (June 1967).From 13th Annual Meeting of the American Nuclear Society,

San Diego, Callf., June 11–15, 1967. Sae CONF-G70602.

29833 (NiA-S1G12271) NkUTl{ON C1{USS >Ic.C’”llIJNS }t/lt238pu, 24/pu, AND 24tcm, D~ford, C. LO; A1t~r, H. (Atom{~e

Internationui, Canoga Park, Calif.). Msy 1, 1967. Contract AT-(04-3)-701. 142p. Dep. CFST1.

Evaluated neutron croaa acction data for the nuclidea 2S8PU,?{?pu, and 244CM were prc~red for ENDF/B. fJccauae Of the lackof cxpcrlmmrtal data, much OCthe Information comalncd In tht,tieilbrarlca is based on theoretics.f calculations. All c,xpcrlmentaldstn nvallahle through Dt!cembcr 31, 19GGwas Includtd In lhcevaluation. A complcie aet of neutron cross section data waa pre-psrcd for each nuciitfc fnr incident neutron energies b~twecn 10+and 1.5 x 107 eV. These data in the ENDF/B format are ●valrablefrom thq Cross Section Evaltkztion Center at Brookhavtm NationalLaboratory, (auth)

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48

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1967

i 7Z7Q (RPI-328-71) LINEAR AccELERATot(PROJECT.AMUd Tw+nlcal Report, July 196&Sep&rtber 1966. Gaerttner,Erwin R. (Rcrmeelaer Polytechnic hat., Troy, N. Y.). Con-tract AT(30-3)-328. 97p. Dep. mn. CF9TI $3.00 oy, $0.66 tttn. ‘

The scnslt{vity of n neutron-capture detector topmtnpt neu-tron scnttcrln$ was Invmtlgntcd. Thr capmre cross sm.tlons ofAl. FO. ‘Fe, f P@, ‘Fe, Nl, ‘Nj, ‘“Nl, ~fN[. ‘{NI, ~nd Na ~cronir.lw!! ( (1 !It rnrrglcs from nlmut 10 krV tO n fvk h!!nrlrcrl kcV.Thr total nvWtrOn cross sectlnns nf ~, To, W. 1M2w,fq4\v, ~~d~RcWw.rr. mrasurcd frmn 0.4 to 20 hlcV. (Xrmrnn spm’lrn fromneutrtw cwpturc Ijy Isl,lg, !!911K,18ZWI,“n~ IR~Wwere mmlyscd;trnnsitlnn strcn hs wrrr obtalncd. The nvcrngc nvutrrm num -

Tbcr/fission of z’ [l was measured over the neutron cnvrg~ rangefrom 2.5 to 9,0 cV, nnd the scattering cross sectlon:l “f ~Bw,23’1/. nnd Z!st! ~erc ~efl~ured for neutron cm rgh tJdWWm ~ afxf .100 cV. Prclimlnnry tmnsmlsslon measurcrncnts of the neutrontotal cross seCtlOns of 14Tpm and ‘Wpm werC mad= OVCr theenergy range from 1 CV to 2 kcV: a graphical area analysis wasperformed to obtain parameters for the 15.6 eV 14TPm resonance.Time-de~ndcnt neutron spectra were measured in light water,and a computer program was written to ~al v.ze the data, Afacility for stud~-ing low-energy neutron ine Iastic scattering wasinvestigated, and mcasurementa were made for scattering bypolyethylene, NbH. ZrH, nnd UOV Codes were also written to .nutomate data reduction. Transient radiation effects in SiIIconwere investigated using a pulsed 50-MeV eluctron beam. (D. C. W.)

11’?s2 (COO -1573-6) NEUTRON TOTA”L CRO& SECTIONLll .W.(’1{EMI::4”1S LIStNG A “IVHIIE” NEUTRON SOURCE.Galloway 111, 1,. A.; Shrmler, f?. F. (Case Inst. of Tech., Cleve- ,land, Ohio. Dept. of Phy~ics). S~pt. 1966. Contract AT-(11-1).1573. 131p. Dep. mn. CFSTI $3.00 CY, $0.65 mn.

A Inethod for measuring neutron tetal cross sections using aneutron intcns!ty spectrjm continuous in enerfiy (a “white” spec-trum) and a pul.;ed beam time -of-f ll~ht technique is used to mea-su~ e nrutron total cross sections in the 2 to 10 MeV region. Totalcross sections for the Clcnlenls Mg, Al, Ca, k“, Fe, Pd, ~ andPb w?rc men.,! red to 1% average uncer~inty in steps of 0.08ns/m Encrqv resolutiorr varied from about 1.5% at 2 MeV to 3%at 10 MeV. Rt,sults of these measurements are compared withmcasuremell@ on the same sompl~s with neutrons of known energyand with measurements of other workers. (auth)

2653 (BNL-325(2ncl Ed.) (Suppl .2)(V01.2A)) NEUTfiON CROSSSECTIOSS. VOLUME UA Z = 21 TO 40. Goldberg. Murrey D.;Mugfmbghah, Said F.; Magurno, Benjamin A.: May, Vlcioria M.(Broekhaven Nationrd Lab-, UptOn, N. Y.). Feb. 19613. COntractAT(30-2)-Gtm-16. 393p. Dep. mn. CFSTI $4.00 cy, $1.75 mn.

An updated compilation of thermal cross ecciiorw, resonanceparameters, and crcen-eectlon curves 18 presented for elementssnfl iROtnpWI with z = 21 to 40. The reference aourcea are alsoinvluflwi. (D.C. W.)

11919 (BNL~32S(2nd Ed.)(SuppL2)(Vol.2 B)) NEUTRONCROSS sEcTfONs. VOLUME IIB. Z = 41 TO 60. Geldberg,Murrey D.; Mughabghab, Said F.; Purohit, Sur@ufra N.; Masum%Beo]amin A.; May, Victoria M. (Brookhaven National Lab., UptOZ2,N. Y.). May 1966. Contract AT(30-2)-Gcn-16. 416P. Dep. mmCFSTI $3.00 cy, $0.65 mn.

A compilation of neutron cross sections and resonance P-rameters is prestinted for nuclei with Z = 41 to 60 Ior oeutmnenergieJ between O and 200 MeV. The energy dependence of thec~oss sections is stressed. (D. C.VJ.)

. .

Neutron Cross Sections;

2. ENDF/B Tapes. ..

13783 {GEAP-S272) EVALUATION A~” COM&ATION OFz3~~ CROSS +ECTION DATA FOR THE ENDF/B FILES. Greeb-ler, P.; Aline, P, G.; Rutchins, b. A. (General Electric Co.,Sunnyvale, CalIf. Advanced Products Operation). Dec. 1966.Contract AT(04-3)-189. ?Op. Dep. mn. CFST1 $3.00 cY, $0.65mm.

A extensive evaluation of 22% neutron cross-section datawaa qzade, and a aet of recommended valuea wag compiled fortbe Evaluated Nuclear Dat&Filee @4DF/B) be~g set up atBroekhaven National Laboratory. This work waa done as part :of the cooperative effort by the Cross Section Evaluation Working ‘Group to put toge2her an ini2ial ENDF/B cross-section file thatwill ioclude moat of tbe materials that are Imperksnt for reactor ‘mzalysia. Tbe recommended ‘SSPU cro&s-sec\ion data extend inenergy from tberrmd to 15 MeV. Recent experimental work, such

“amthe Petrel bomb test data, and previously unreported theoreticalwork that provides a firm basis for the seiectfon of resonance ‘~ammeters In tie unresolved resonance region are taken intoaceoum. Data sources are summarized and are followed by aeamplete documentation of tbe evaluation anslysia and a listingof the se,lected data. (au@)

1077 (LA-DC-?813) NEW-TIME-OF-I LI~;IfT’MEASUREMENTS MADE WITH AN INTENSE SOURCE.Heinmcndlngor, A; (Los Alamo8 Scientific Lab., fln!v. Iof Calf fo2nta, N. Mex.). [19661. Contract W-74~)~-er2g-36. 51P. (CONF-661O14-B). Dep. mn. CFST1 $3.00 CY,$0.50 mm

From IAEA Conference on NucIear Data, Pa~& France.In an experiment in Nevada in June 1965 a nu$lear device

WIU2 a yteId equivaltmt of 1.2 kton of TNT provided the neu-troh source for time-of-flight measurements over a pathof 185 m in W2CU0. To exploit the combination of high fluxand ,high ener~ resolution, new recording techniques wererequired. Because more than a million data points areacqu 1red in any one exposure of a set of targets, the gen-eral problems of data retrieval and prcceeaing requiredspeclai attention. Measurements of fission cross sect!ortaor the nuclides ‘S3U, 288U, 2soPu, ‘toPu, 24*Pu, 241Am, and242Am’ are rc Ortedo In 6ddltion, capturC-@-fieSfOn ratfOO

rof 222U snd 24 Pu ate reported. The neutron energy rangeiR 10 eV to 2 McV. Individual reeonancee are reeolved inthe 100-eV rsngc. Fisslo~ data in the resonance regionarc characterized by lower minima than are re~rtcd b7moat earlter inveetlgatore, indicating more favorablealgnnl-to-background rptios. A unique feature of theseexperiments, is ibc high rate of dnia acquisition, whichallows cross-section mensurbmenta on short-lived nu-elides. Even for fhe long-lived nuclides, these experi-ments provide an abundance of data required in currentnuclear technology —data that could otherwise be acquiredonly by years of tedious meam!rement. (auth)

49

1967 Neutron Cross Sections:

.- 2. ENDF/B Tapes. .------4274

1(GEMP448) EVALUATION AND COMPILATION

0F111Ta,18zW, lUW, lMWOAND IUW CROSS SECTION DATAFOR THE ENDF/B FILE. Henderson, W. B.; DeCorrevont,P.AJ Zwlck. J. W. (General Electric Co.. Ctncinnatl, Ohfo.Nuclear Materials and Propulsion Operation). Nov. 11, 1966. “Contract AT(40-1)-2847. 91P. Dep. mn. CFSTI $3.00 CY.$0.65 mm

Evnluatcd neutron cross section data are gtven for 181Ta, ‘6qV,1%1, 184W,and lWV. The resolved resonance ranrc is soccificrftocxtend upward from 10+eVtothcpohst at haif’’the ie;.ei spac -Ingnbovctheltwt resolvcdresonnnco. Thelowwr ilmllwasplckcdto ensure that at room iemncrature. and above. errors of the orderof 1’%m’ icss wmsid bc incurred by negiccilng reactions bciow thecutoff, The single-level f3reit-Wihmcr formula for s-wave ncu -tmns wus uscdina cmdctocomputepolnt vaiucandlsstcgml crossscctlons. No Doppier broadcnlngor solld-siate effects were {n-ciudcd. Noattumpl waa made to compensate for inadequacy of theaingft!-levci formuiaby smooth cross sections. A singiencgativeenergy ievcl was used in each isotope to improve the fit to mca -surcdalx60rptlon andtctai cross sections Inthc tbermaf range.Thovaiues assigned nreregardcd asprellmlnary. (S. F. L.)

21410 NP;(ITI1ON CROS3 SECTiONS OF IiYDROGEN IN THET:NFIK; Y RANGE 0.0001 eV TO 20 MeV. Horsley. A. (AtomicWeapons Research Establishment, AkfermafXfw EwL). N12ci.Ddn, Sect. A, 2: 243-62 (Sept. 1966).

Thcorctlcai and experimental data for the neutron cross sectionsof l}f arc aurvcycd and vaiues recommended for total and partialcross acctlons In ihe energy range from 0.0001 eV to 20 MeV.Avallablc experimental data are supplemented where necessary byestlmatcs based on nuclear theorv. Details of energy and angular

,

dependence arc given so that the ~ata are compiete-lor the purfmsesof ncutronlcs caiculatfoqs. (85 references.) (auth)

11968 0 (OfIMP-470) BERYLLfUM NINETEEN GROUPCROSS SECTIONS. Kamphouae, J. L. (General EIectric C%Cincinnati, Ohio. Nuclear Materlaia d Pmpulaims Operation).Mar. 20, 1964. Contract AT(40-1)-2647. 33p. Dep. mn. .CFSTI $3.00 CY, $0.66 mn.

The nineteen-group bcryiiium cross sections have been revisedusing the moat recent data. The entire probiem of the treatmentof beryilium is bclng investigated, and the status of that work isgiven. Special emphasis is given to the treatment of the (n,2n)reaction. (auth)

17353 (KFK455) CAPTUR~ &ROSS-5 ECTION MizAsuRfi- ,MEt4Ts FOR SOME MEf)Iuhf AND i3EAvy WEIGHT NucLEIUSING A LARGE LIQUID SCINTILLATOR. Kompe, D. (Kern-forschung~zcntrum, Karlsrube (West Germany). fnstltut fuerAngewandte Kemphysik). Oct. 1966. 12P. (CONF-661O14-44).Dep. mn.

From IAEA Conference on Nuciear Data, Paris, France.Neutron capture cross scctlons for the nuclei Ag, Au, Cd, Cs,

Hf, In, Mo, Nb, Pd, Re, Ta, and W were measured in the energyrange from 10 to 150 keV using a pulsed Van de Graaff generator,A large llquid scintillator was used to detect capture events inthe samples. All measurements were based on the capture cram●ectlon of Au as a standard. (. S.F.L.)

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tI

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11916 (ANL-6172) TAB~ES OF ‘DfF~EREN’r~L CPOSSSECTIONS FOR Scattering OF NEUTRONS FROM VARIOUSNUCLEf. Lane. R. O.; Lengadorf, A. S. Jr.: Monti’m. J. E.:EIwy12, A. J. fArgonne National Lab., Ill.). [ndl. contractW-31 -109 -eng-36. 226p, Dep. snn. CFSTI $3.00 cy, $0.6S mn.

Experimcniai values of the neutron dtffercntiai ecnttrrlng cress~cction~ of 9B0, Ca, !2c, I%, LI, 4LI, lLi, 160, S1, S, and SISaretsbulated, together with values obtained by a lcaei-squarrs fittingof the data, and the error matrix resuitlng fm.m the hmtit squarracalcu~atinn. (D. C.W.)

loobt (LA-3586) FISS1ON CROSS SECTIONS FROM PE-TREL. (LOS Alamos Ecientt ffc Lab., N. Mex.). Sept. 1901966.Contract W-7405 -eng-36. 231P. DeP. mn. CFSTI $3.00 CY.$0.65 mh.

Fission data obtained in the Petrei event of June 11, 196S, ●represented ~aphlcally and in tables, inciudin calculated standarddeviations. The lsotope,s studied were 2S3U, 3$U, 238~* mm,Ztlpu,Z{lAM,@ Z4zA~:then~utrorsenergyrsssgcCovereff for

meet isotopes was 20 eV to 1 MeV. (auth)---- ---- ------- .-

,,31810 z~:cf FISSICJN NEt-IT~ON SPECTRUM FROM 0.003 ‘TO15.0 MeV. Meadows, J. \V. (Argonne Nationai f.sh., fll.).Phys. Rev., 157: 1076 -82(MnY 20, 1967).

The sfmrdaneous-fission neutron spectrum of ‘i~f was mea- .sured from 0.003 to 15.0 hleV by time-of-fllght techniques. A ohydrogenous liquid sclntl Ilator wae used as a detcctnr at thehigher energlcs, widic n ‘1.1-hmdcd glass aclntiliator was usedat ihe lower energicst The measured spectrum has an averageenergy of 2.3 t8 MeV. A Mnxwclllnn distribution, N(E) ‘“ E~ QxP(-E/ l.565), fits the data well for 0.5< F < Imn Met’. Ikiow 0.1MeV, N(E) has a fi dependence but with values ‘25!% larger thanthose predictccf by the extended Maxwellian spectrum. The re-sults are interpreted in te~me of a simplified evaporation model.(auth).

9995 (AEEW-M-504) NEUTRON CROSW;f’llONS F(IRNA”l_URAL ZIRCONIUM IN THE ENERGY IIANGE O.0(11~1et’ I’ll6 kcV . IkJpe, A. L. (Atomic Energy I?stablishrnm:t, Wlnfrlth(Engiand)). Sept. 1966. 26P. f’2cP. mn.

The avullnl)it’ rmmivrd rcsonnncc tinin fnr ihc Isot,qwn t~f 71rco -nium nrv rv;IluniL’d, wIth tho vlrw to compllr a file 01 IIIOIC l!lhu-i:tlcd nvutr!m cross -ricction dnin. These dntn nrc :Ii.o.omlmparwfwith intc~tmlly mvapurcd dain: and from the discrqmn,+w 11 1sconriudcd that there Is a need for bcitcr mmsurcmcnls of the radi-ation widths of the resonancca for aii zlrcnnium iaolojws, espe-cially for ihe s-wave rcsonancm of StZr; thai the rneatiurrd Wlueeof the thermal neutron cspturc croea sections of the {RCI1OPV6nrcnoi conslstcni with the data for nntural zirconium: nnd thnt fh,’rcarc stlli considerable uncertainties in the resonance abaeI ptlnnintegrals bnth for naturai zirconium and the separated lsetuue~.(auth)

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1967.,

23i41 ~ (KFK-120) NEUTRON“CROS95ECTIONS FOR FASTREACTOR btATERIALS: PART I. EVALUATION. Schmidt,J. J. (Kernforschungszentrum, Karltmube (West Germany). In-stitut fuer Neutronen@iysik und Reatdortectudk). Feb. 1966.1317p. Dep. mn.

A compilation of neutron croms eectlcmi and reeenaoce param-’ ““,qters for C, Cr, He, H, Fe, Ate, Nl, O, ‘S%, Na, 2S5U,and’23eU 16presented. The techniques that were used tn the anslysea of thedstx are described. Neutron energies in the range from 0.01 eVto 10 bleV a~e-cpve$ed., (D. C.W.).

.,, . .. . . .23487 ‘“F1SS1ON CkOSS SECTIONS OF 241AmfiND 242mAm.seeger, P. A.; Hemmendinger, A.; Diven, B. C. (LorI Alamos “Scientific Lab., N. Mex.). contrapt W-7405 -eng-36}. McI. Phya.,,A96: 605-16(1967). (LA-DC-7624).

The acquisition and enafy.sia of neutron oross section data froman experiment using en underground nucle~ detonation are dis-cussed with specfflc refeswnce to fiesion cmse sectlone measuredin the Petrel event in Juge “1965. Results are presented for 242Amand 2LmAm over the energy range 20 eV to 1 MeV, measured si-multaneously in s sin@e experlzqent covering the entire energyrange, with very low background. Considerable Isub-threshold fts-.sIon was observed for 2tiAm. The fission crose section of the , ‘doubly edd nucleide 2eAm Is about twice that of 21% over mostof the neutron energy range, but only about 20% &eater at 1 MeV.(auth)


2. ENDF/B Tapes. ..

. . .. . . . . . .,i-~ Rsdlatloa LabJ . cQlitAat W-?itifi-e~-48. 63p.Dep. ma. CFbTl $9.00 oy, $0.66 mn.

Tbenretlcai studies were made of N-N acatterbzg, electronscattering by pnlyatOmic moleculen, A-N Interactldz, ~Hc”, the

“1fmm-nucle.on a.yblrrn, X -N Interaction, and r-r scatter ng nmpll~tudes. The [isslun croms sections of ‘zmAm and ‘WJ were mea-sured from 0.0? eV to 6 MeV and frnm 0.004 to 2 keV, rurnpcctlvely.Threshold fhll.,neutrou crodrn tmctions for Fe a,nd f3e were alaomeasured, MUwcre the photoneutron cross sections of lDY, ‘OZr,Olzr, ~Zr, and uzr up to photon energtes of 30 MeV. Crosssections for tbe reaction “N(n, M)’4C were obta i,ned from mea-aurementn of the cross section of the reaction 14C(p, ~)14N. Thereaction “C(p, n)14N was investigated at proton energies twtwecm7 and 14 hfeV; the angulnr distributions at the hlghetit energieswere analyzed using a finite-range Dl@A formall~m. Angulardistributions for the reaction 1sF(rr,t)20Ne were anaiyzed ubluga zero-range DW’BA formalism. Differential cross sections for(a,n) reactions on I1O and lBO were measured st !3.8, 11 .G, and12.2 Mew and evidence was slt?o obtained for tne (n,yf) reactionO. ill~ for SIOW neutrons. The neutron scattering cross SeCtiOnSof 2tI~ and WJ from 2 to 32 eV and from 2 to 22 eV, respec-tively, Were studied further.’ Data were aiso obtained on the de-excitstion y rays foiiowing (y,n) and {y,p) reactions on 160: andtbe apmtaneous fission hatf ltfe of ‘zmAm wae meaeured, aawere the thermal-neutron capture cross sections of Ca, 42Ca,tSCS, ad UCa. Neutron diffraction studies of the Magnetir? tran-sition in NiS as a function of composition were carried out.Bounds on the fugacity and virial series of the pressure In mat-ter were obzained, and the magnetization and donducttvtty of Fewere studied from 300 to 1250 kbar. Equation-of-state measure-ments were carried out on rare-earth metals, and eiaatoplasticwave structure generated b Al by a tangentially accelerated ,flytng plhte was studied. A diffusion approximation to the inertialenergy transfer in isotropic turbulence was developed; and atmo-spheric focusing and refraction of blast waves were studied, aswan plasma produ&ion using multiple laser beams. The effectsof various P rameters on the output energy from a Q-spoiledmby oscillator were aiso studied, and the rate of energy trims-fer between electrons and ions in a ~lasma was calculated.(D.c#w.) .“” . .

25399 (ANL-Trane-168) BULLETIN OF”THE INfc)RMA-TION CENTER ON NUCLEAR DATA (l?lRST ISSUE). Translatedby Elmar K, Willp (Argonne National Lab., 111.), from BuylletenInformatsiormogn Tsentra po Yadernym Dennyrn, Atomi zdat, Mos-cow, 1964. 442p. Dep. CF5TI.

Parameters of eiemenfary interactions of neutrone with nucleiare presented, ~gether with reactor constanta. The calculation

. of neutron cross sections by the optlcaf model, usfng computers1s dfscussed, as Is &ta processing for slngie-crystsl fast-oeutmnscintillation spectrometry. (D. C. W.)

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51

1968Neutron Cross Sections:

2. BNDF/B Tapes.. .

16002 (GA-6133) NEUTRON CROSSSECTIONS FOR NIO-BIUM. All~n, hf. S.; Drake, M. K. (General Dynamics Corp.,San Dlcgo, Calif. General Atomfc Div.). Aug. 2.1967. Con-tract AT(04-3)-167. 71P. Dep. CFSTL

The neutron cross acctlona for Nb that have been prepared forthe Evaluated Nuclear Data File (E NDF/B) as Part of the coopera-tive effort by the Cross Section Evaluation Working Group aredescribed. The cross acctions were prepared from acts of pre-viously evaluated data and from dati that were obtained in an at-tempt to complete the existing data. (D. C.W.)

18230 RESONANCE ANALYSIS OF THE 2a3U FISSION CROSSSECTION. Bergen, D. W.; Stlbert, M. G. (L.oa Alamos ScienttffoLab,, N. Me%.). Phys. Rev., 166: 1178-89 (Feb. 20, 1968). G- IDG6946). ,

The neutron-induced fiaaion and capture sections of 22SUweremeaaured by time of flight wfth ● nuciear detonation ●a the neutro.source. Croaa-aectfon data are presented from 20 to 10° eV forfimsion arxt from 30 to 63 eV for the capture-to-fission ratio a.Data In the reeonance region (20 to 63 eV) were fitted both by aeingle-level function conelntfng of a au m of Briet-Wigner Ievelaml by the Reich*More multilevel function based on R-matrixthmry. The resulting resonance parameters are Iiated ntxl din- “cumwd. A study of croem nectfona derivd from twm amf threehypctheticat resonancca ucdcr various conditions of interferenceis presented to dctcrmlne the validity of the rcrmnance parametersdcrivod from the multilevel fit. (auth)

. . .. . -39652 THE 2a$UF1SS’1ONAND CAPTURE CROSS SEOTIONSASD THEIR ANALYSIS AT LOW ENERGIES. Bergen. DebarWesiey. Albuquerque, N. Mtx., Univ. of New Mexico, 1967.7flpo

Thesis.The 211Ufiaaion d capture cross aectlonn were meiewred

using a nuclear-device neutron source and ~ime-of-flight teuh-. . .. —.—- -. . . . . . ,.

niquce. Croaa-eectton dath are presented from 20 to lN eV forfiesion and from 20 to 63 CV for flesion + rapture. The rywmanierrglon (ZO to 63 ev) wae fitlcd with both a aingln-level functionconfiiating of a sum of Drcit-Wigner levels and the Reich andMoure multilevel function based on it-matrfx theory. The rcsult-fng rmmmanre parnmqtcra arc liatcd and dlmcueacd. In orderto cetablieh the vaildity of the rcsonnnce pmamctors derivedfrom the multilevel fit, a study ie pre~ented of the crckmf eeotionderived from two nnd three hypothetical rosonamcs under variou!i

, cmrdltfons and of the croae ecctiona obtained ftu.,i randomly gen-erated rcaonances. (Dia~. Abstr.)

.-.

i822b NELITRON-iNDUCED FISSfON CROSS SEC1’ION OFl{:-Am. Bowman. C. D.; Auchampnugh, G. F.; Fultz, S. C.;ffoff, R w. (Untc. of California. Livermore). Phya. Rc~.,IG6: 1219-26(Fcb. 20, 1968).

The neutron-itiuced fission croes section of 2’~mAm wae tnca-”surcd from 0.02 CV to 6 MeV by the time-of-flight methcd attheLi~ermorc 30-McV linear elqctron accelerator. The data areeormdized at 0.n253 e\’ to a value of fj600 b mcnsured M a re-actor thermal-neutron flux. The croaa section at 0.2 eV ia 4700 b,at 1 eV it is 540 b; and at 4 MeV it ia 2.1 b. The data ●re analyzedto obtnin valuca for the neutron atreagth fimctfon (T ~D) of 1.4 X10;’. the lc~el SPaCIW D = 1.2 eV, ati the quantity ~r@(/D) = 2.5.All three quantities pre quoted per spin date. The high nross sec-tton at low energlea can be attributed to the unueuaily high valuefor 2r T~/D). and to the cxiatence of a very large resonance at0.173 ev. The firia~on croaa aectiOn of 24tAm alSO wae me~auredto the MeV region and found to be 4.96 ● 0.2 b at 2.5 MeV. (auth)

-.

24873 SELECTED F1SS1ON CROSS SECTIONS FOR ‘%,salu, atb”, ?SCU,!t9ff, ~?f’@, M*I-J,‘%, ‘ok, ‘h, AND ‘Pu.

D&ey, William G. (ArgOMe National Lsb., Id~o FaUe~ Id@).NUCL SCI. Eng., 32: 35-4 S(Apr. 1963). ” “

The fideinn cross sections of 2nTh, lUU, 2XU, 23iU, ‘MU, ‘nNp,:scu, lS8pu, NOpu, 2ttpu, ~d z~lpu from 1 keV to 10 MeV published

up 10 July, 1965, were analyzed previously td select best fiaslon“cross aectfona for faat-r~actor ana.lyaia. s~ce. tie completion ‘fthnt work, new data have been produced which necessitate reeval-.uatlon of the fleaion croa$ oecttona parttcalarly tn tbe regton 1 to6 MeV, The revised data presented here are believed to be of

“ greatkr consistency mid, hence, acc,uracy than the prevfoue selec-tion. (auttr)

‘ 27289 (AERE-R-5224) THE AVERAGE NEUTRON TOTALCROSS-SECTION OF 10B FROM 100 eV TO 10 MeV AND ABSORP-TION CROSS-SECTION UP To 500 keV. Dlment. K. M. (AtomfIY.-Energy Reaezrch Eetttbltsfunent, Harwell (Engla~)). Feb. 1967.17n. Den. C FSTL UK.

“T-hetr~nsmi.sslon meamtremente to be d?acrlbed were made onthe 120Tm and 300-m ftfght pntha. of the Electrnn Llnac tlmr-or-ff{ght spectrometer at Harwell. Analyets of the total crosn eertionbelow 10 keV shown UrJ,T= (610.3 * 3.1) @ + (1.95 * O.1o1 b~rn~.

, The deviation of U=,Tfrom thfq value ●bove 40 keV is due to in ln-creaae in elastlc ecattertng croem section. Subtraction of thelatestocatterlng cross aectiona meaeured by Mmrlng et al. ytelds anabsorption croar ❑ectlon that to proporticmat to E_~ up to at leeat260 keV. (autfd

16001,,,pa, AND\~&~7’62) NEUTRON CROSS SE6TIONS FOR~Stpa,Drake, M. K.: Nichols, P: F. (Gulf GeneralAtomic, Inc., San Diego, CalIf.). Sept. 8, 1967. Contract AT(04-3)-167. 63P. ‘ DCP. CFSTI.

A survey wna rondo of tho nvnlbrblo oxpcrlm~ntnl croes-scction mcnnuremcnts for 2$tPa, ‘s3Pa, nnd 2S2U, Scta of rocom-

‘ mended neutron croaa ncctionn nnd rcannanco pnrnmctora ●reprctwmted for nculron enorglcs from 0.001 OV to 15 MoV. (D. C.W.)

.

.

.

.

52


2. ENDF/B Tapes. ..

16003 (GA-4135) NEUTRON CROSS SECT1ONi FOR23:U””AtifJ 2S6U. Drake, M. K.: Nichols, P. F. (Gtilf General Atomtc,inc., Snn I)lcgo CalIf.). Sept. 1,1967. Contract AT(04-3)-167.76p. 12ep. C FbTL

A aurvcy was mnde of tho nvnilablc cxperlmcntal cross- ,m$r!k!n mcnsuremcnta for ‘S4Uand UeU. Sets of rccommcttdcdntulr,, n cr08s scctlona a,re prcecntrxf for neutron energies from0.(101 rVto 15 McV. Resonnncc parameters are also Included.ff-l.c.w’. )

. .

37310 (AD-665363) NEUT1{ONANDGAhl MA NAY PRODUC-Tl<’NCl\O<+ Sl:(:rl\)NS FOI{SC21)1UM, MAONltSIUM, Cli LORINE,~) TA.<<Illhl, AN[) CA LC[(IMO I~A]{T v. pOTAs$lUM, Drsf@,hl. K. (General L2ynamlcs Corp., San Diego, Cnllf. GeneralAtornlc Div.). Nov. 1967. Contract DA-18 -035 -A MC-730(A).133P. [GA-7829 (Pt.5); NDL-TR-69(1%5)). CFSTI.

Au lnvrstigatlon was made nt the neutron Interaction proba-hllltlrs with the element pctasslum. Sets of rccommemfcd totalnnd partlsl neutron cross rwctlons were prepared. The energyawl angular distributions of the secondary neutrone are given.Ahm, gamma-ray production cross sections were cbtaincd aBwell aa energy and angular distributions of the secendary gammarnyq. In general, the recorwmendcd data were based on cxperl -mentnlly measured data. However, where no experimental datawere available, the recommended cross sections were obtainedusing model calculatlona. (auth) (USGRDR)

13904 (LA–3801) ENDF/B FORMA r REQuIREMENTs FORSHIELDING APPLICATIONS. Dudzlak, Donald J. (comp. hnd cd.)(LOS Alamos scientific Lab., N. Mex.). Apr. 1967. ContractW-7405 -eng-36. 52P. (ENDF-111). Dep. CFSTI.

The present (April 1987) Evaluated Nuclear Data File/B(ENDF/B) format waa designed primarily to satisfy the require-ments of nuclear reactor core neutronics calculations. Exten-6{On9 of the format apec{ficationa are prt,p, ~sed to Include dataof in~erest for shie iding calculations for t eactor and other ap-plications. Alternate methods of presenting the necessary rfataare discussed, and the correspondence of t?NDF/B to the UnitedKingdom Atcmlc Energy Authority Nuclenr Data File (ifK) ismaintained wherever practical. In the case cf photO,, interac-tions, detailed formats are recommended for cross sectionsfor secondary angular, energy, and energy-angle distributions, andfor incoherent and coherent scattering at, ]mlc form factors. For-mat recommendation for photon productirm data include th~sefor photon angular distributions, photon production multiplicities,and photon energy-angle distributions. A listing of data on photoaproduction in Na Is inciuded. (auth)

11936 NEUTRON TOTAL CROSS SECTION hlFASURfZMENTSUSING A “WHITE’” NF.UTRON SOURCE. Galioway 111, louleAltheimor. Cleveland, Cage tnst. of Tech., 1966. 131P.

XWf%d (“r measuring ncufron toil] crms section. using anmttrsm intrnqlty spcctnlrn c,mtinla,,llx in c“,$rIu (n “wkltc.”” .OpeC-t rum) nnd ~ pulwfl lwanl t ime-of-fl lgl!l Ie, hnkpw WISIused tonlrvtsurc nculrfm total cross rwetkma in the 2 (0 10 MOV rc~irm.Tolml cross sections for tlw (Olrmm}tg h?g, f\l, (’n, V, ~i,, Pd, Agand Ph we rc mrasurc(l to 1’?,avcrafy !Inccrl:dnly in strlm of 0.08ns/m. l(ncr~y resolution vnrir[l fr,m, aijout I .5’&af 2 fif~v to 3%at in Mel’. Results of these njeas,, rcmcnts arc COmpIrC~ withmeasurements on the same samplrs with ncul runs of known energyand with mcasurcmcnts nf dhcr workers. (Disscr. Abatr.)

. 37307 (AD-665360) NEUTRON AND GAMMA RAY PRODUC-TION CROSS SECTIONS FOR SODIUM, MAGNESIUM, CHLORINE.POTASSIUM , AND CALCIUM. PART H. SODIUM. Garrison,J. D.; Drake, M. K. (Generat Dynamics Corp., San Diego, CalIf.General Atomic Dtv.). Nov. 1967. Contract DA-16 -035 -AMC-‘f30(A). 148P. (GA-7829 (PL2); NDL-TR49WL2)). CFST1.

Neutron and gamma-ray production cross sections acts wereprepared for the element sodium. These data sets lnciude totaland partial neutron cross sections as well as the cross aectionefor producing decxcltaiion gamma raya. Information Is aisogiven for lhc angulnr and energy diatrtbution of the secondaryneutron and wrm mn raya. (auth) (USGRDRJ

22584 (~-”~-g~~~) ~~tu NEUTRON CAPTURE RESULTS

FRC)?d M3Mif .M)[JffCfi NEUTRONS. Glaea, N. W.; Schclbcrg,A. IJ.; Tatro, L. D.; Warren, J. H. (Los Alamos Sclentlfic Lab.,N. Mex.). [1967]. Contract W-7405 -eng-36., 18P. (CONF-660307-20). Dep. C FSTI.

From 2nd Conference on Neutron Cross Sectione and Tech-nology, Wnshlngton, D. C.

ficsults on neutron cspture In 238u from 30 LO2050 CV ncutrcnem.rgy arc prcsr.ntmi. The data were obtained by neutron t~mc-of-fright utlliztng tbc’ pulse eource of neutrnns from the W-trelnuclear caplosion. The tetai radiation width, 1“,, was dctermfncdfor 621 = O Icvcla with ~7 = [19.1 * 0.6 (stat.) * 1.4 (syst.)] x 10-$cV. There app~ara to bc a significant variation in the value of l_rfrom rcaonance to rceonance. Approximately 200 weak rceonanceewere fcund whtch can be ascribed to p-wave Ievcls. Armlysls ofthese weak resonances, aaaurnlng 1 = 1, gives reaulta consistentwith: an average reduced neutron width of 3.7 + 0.7 x 10-J eV: anaverage level spacing of 7.0 * 0.5 eV: and a atrengtb functikm of1.8 * 0.3 x 10-4. (auth)

20561 (AIISI!(3)N-141) NEUTRON INTERACTION IN TiiflENENCY RANGE 1.0 E-10 McV TO 15.0 MoV. Nnrt, w. (UnttedKlnudom Atomlr Energy Author!ty, Rintey (England). AuthnrltyHrslth and Snfety flrnnch). Mar. 1968. 42P. DCP. C FST1.UK.

In the pwii (W ymrn. some high-resolution measurements bnvehem lw.rformmt which, when combined with thwmcltcal predlctlone,afford a rtebIilerf rirsr-rlption of ne,ltron Inlcractlrms wiih the nu-cllde tnntaium. From these aed othor sources of information, 1

. ..- / .,. .act of nrutrrm crnnfi em-tiona and other relcvnnt paramotern havehcun cvnluntcd. Thry cover the cn~rsy rnngc 1 x I n-lo tn 15 MeVand arc prcsrntcd nb a ncw tiatn fiIe (DFN346) for the UKAEANuclear Datn Llbrnry. (auUr)

. . .— --— .29838 CURVE FITTING AND STATISTICAL TECHNIQUESFOR LISE IN TIf E hlECNANfSED EVALUATION OF NFTrTR(INCROSS SECTIONS. Horaley, A.; parker, J. B.: price, J. A.(Atomic Weapons Research Authority, Aldermaston, F.ng.l.Nucl. fnstrum. Methods, 82: 29-42 (June 1, 1968).

A cubic splint curve flttlng method and a stmtistlcal thwry ofunknown sytrtcmrdtc errors are combined to give a prnrth?atcomputer-orientated methed of evaluating neutron cross sw, tions.Particular attention Is paid to reconctflng SCM of diecord:int data.The Input dais and evaluated curve can be dlsplnyed on II C [{Tgrsphtcal display unit. Among program output examples gtven areevaluated curves for severat cross sections of l%. (auth)

53

1968

29094 (LA-3271) EVALUATED NEUTRON CROSS SEC-TIONS FOR DEUTERIUM. Horrdey, Anthony :Stcwart, Leone -~l,ea Alamoasclentlflc Lab. $N. hfex.). Nov. 1967. 139P.Dep. CFST1.

A compUatlon of evaiuated data on the neutron cross aecttons ofdeotcrlum Iapreaented forlncldcnt neutron cnergloaof 0.0001 R=Vto 20 MeV. Thedata are displaced In gmphlcsf and tabular form.Lcgcndre coefflcltmte are included for the scattering angular dla-trlbutions. proton epectra from neutron end protan reeetfone withdcutcrlum nro nlRo Included, na aro proton frroductlon crow! ncc-Nonq nml nvutron production crofm scctlotw. (11.C. W.)

.48446 NEUTRON CROSS SECTIONS OF fJIX.TfilUUM INTHE ENERGY RANGE 0.0001 eV TO 20 MeV. Horaley, A.(univ. of Birmingham, Eng.). NUCL Dab% *cL A. 4: 321-57(JuiY 1968).

Experfmentat and Ureoretical data for the neutron crorm sec-ttous of D are surveyed, and valuea are adopted for totai and~rtial cross ~ectiona. To faciUtate neutrordca calculation,angular distribution functtons baaed on n + d and the conjugatereaction p + d are given. The experimental data used, with somecomments, and a brief accountof the evaluati~~n procedure arepreaerrted. (autb)

3607 (ORNL-TM-1872) ‘EVA~UATION OF NEUTRONCROSS SECTIONS FOR 10B. Irving, D. C. (Oek Rkfge NationalLab., Tonn.). Oct. 9, 1967. Contract W-7405 -eng-2& 45P.Dep. C IWT1,

The neutron croaa acctiona for % were evaluated from 10-( eVto 15 McV. The existicg cxperimcntai data arc reviewed, andIhroreticnl calculations arrd other reasontng are used to fill inthe ~q>a. A complrte and consistent set of.cross acctions is pre -scntml, and ao explanation is given for the choices made in devel-oping this cross-section act. (auth)

... .35627 GROUP CROSS-SECTION SET KFK-SNE~K.’ PREPA-RATIf )N ANfJ RESULTS. Kucetem, H.; Bactunsmr, H.; Huscbke,H.; Kloffmber, E.; Kricg, B.; Matratroth, M.: Siep, 1.; Wegnor, K.;WO1l, D. (Kernfornchungezemtrum, Karlerube, Oer.). PP’167-88of Eant fieactor Phyaica. Vol. L Vienna, Irttarnetlottel Atmnto ,Emr~ Agency, 1968.

. .

From Symposium tm Fnot keactor Pby&c’e & &labd SafetyProblems, Kerkuhe, Germany. &e STf/PUB-185WoLl);CONF-671O43+OI.1). ,

For tho caicuiatlon of integral quantities, rrteaeured in the FactZero-Power Assembly SNEAK, a new group croaa-section aetwae prepared dtrectly from microscopic data. These data arebaaed on the latest evaluation of craaa-section and reaonsnceparameter tabulated on the Karl sruhe Nuclear Dztz File.KEDAK.special attention ie paid to the calculation ot the elantic madera-tiono (auttd


2. ENDF/B Tapes. ..

46695 [fiflfl FNR-537) TABLES OF EVALUATED NEUTRONCROSS SECTIONS FOR FAST REACTOR MATERIALS. Langner,[.: S( hmIdt, J. J.: W“ll, 1). (Kernforschungszentrum, Kerlarube(West Germnny). tnetltut fuer Neutroncnphysik und Reaktorkcch-nik). Jan. 1968. 663p. (KFK-750; EUR-3715; EANDC(E) 438-U).

W’ork Performed umfe r wtited States-Euratom Fact ReactorExchange Program.

Tables of evaluated data, irs functione of incident neutron en-ergy, are preacnted for the neutron cross sections and rcaonanceparameters of materlafa that are of prr~ticular interest in the de-sign of last arid intermediate reactora. The’materisie coveredInclude C, Cro He, N, Fe, Moo Ni, O, 2S9PU, Na, 2JSU, SIXI2J1u.(D. C. W.)

35195 (AEEW-M+02) U. K. A.E.A. NUCLEAR DATA LI-BRARY, JANUARY 1967. Norton, D. S.; Story, J. S. (AtomloEnergy Eatablfahment, Winfritb (fJ’@rrd)). Feb. 1966. 19P.Dep. CFSTI. UK 3a. 6d.

Detaiia arc given of the UKAEA Nuclear Data Library aa .ofJacmry 1967. The updating of the Iibtary included the incorfmra-tion of several new data filee, t.ngether with the extension of rangeorrf come older fiiea. (autb) .,

50559 (ANL-7387) COMPILATION OF k>,; F/fi D.4TA FONMAGNESIUM, TITANIUM, VANADIUM, MOLYRl)kNU,U, ANiJG.\ DULINIti M Pem.itrgton, E. M.; Gzjninfc, J. C. (Ar#umwNational Lab., 111.). Mar. 1968. Contract W-31 -10 Y-eug-38.122P. Dep. CFSTL

The compilation of ENDF/B neutron cross-scctfon data forUre materiala magnesium, titanium, vanadium, molybdenum,and gadolfnium is presented. AIi tire data in the ENf_)F/B formatare iisterf, and graphs of much of the data are prccented. (autb)

22615 AVERAGE CROSS SECTIONS AND RESONANCEINTEGRALS OF 242mAm. Pcrkfns, S. T.; Auchampaugh, G. F.;Hoff, R. W.; Bowman, C. D. (Univ. of California, Livermore).Nucl, Sci. Eng., 32: 131-2 (Apr. 1!360. (UCRL-70735).

The energy drpr=ndence of the neutron fission cross of ‘tmAmwas investigated from 0.Q2 eV to 6 MeV. The measurements

%vere normaitzed to a value for the fission txosa aictlon M 6600 b‘at 0.0253 eV. Beiow 3.7 eV and above 300 ke eV, the cross me-tion wae corrected for 2~fAm in the sample. Tbe data ●re prese~in terme bf mean values and resonance bttegrala aver the CAMgroup atiwcture, The resonance integrai ●boye 0.5 eV ia 1570 ●

110 b, The data beiow 3.5 eV were analyzed in termo of ● mtnt-of-ehgle-levele fit. For the SIX renonancea beiow 3.5 eV, thaaverage fiaaion width Ie 0.46 ~V. (D.c.w.)

46730 \APDA-217) EVALUATED NEUTRON CROSS SEC-TIONS OF 1 Na FOR THE ENDF/B FILE. P!tterle, T. A.(Atomic Power Devoiopment Asmcietee, Inc., Detroit, Mich.).June 1968. Contract AT(ll-1)-865. 43P.. (ENDF-121). Dep.C FST1.

An evaluation of nNa neutron crone aectfon data was carriedout for the END F/B file. Data were evaluated from 10+ eV to16 MIZVfor the foliowlng neutron mactiona: totai, eiaattc acst -tering inciudbrg fagamtre polynomial expanalorm of tire angulardependence, nanelaatto, ineiaeUo tncluding reaolved Ievela, (n,y),(n,p), (n,a), and (n,~). Grapbe of the ●veiuated data am com -pued with expertmenfal data. (attth)

54

Neutron Cross Sections:1968

48508 (APDA-218) EVALUATED,NEUTRON CROSSSEC-TR>NS OF ~~olm FOR THE llNDF/fl FILE. Pitterle, T. A.;YRrnnmoto, M. (Atomic Power Development Associate8,1nc~, “Detroit, hllch.). Juno 1968. Contract AT(ll’-l)-666. 60p.(ENDF-122) DCP. CFSTI.

Data wcreevnluated from 10-~to 15 MeVforthe following neu-tron rrm-tlons: tOtal. n-~, ftaslon, (n,2n), (n,3n), elnsticscattertngbcludhg kgrndre~l~omlal espsneions ofthcnngulardcpen-dcncc, nonclaptic,am tinelastlc scattcrbrg lncludtng resolvedIevcl.s. Grnphsof thcevaluated data arelncludcd. (quth)

16012 (KAP&3327) EVA LUATEDCROSS SECTIONS FORTHE HAFSI[iM ISOTOPES. Reynolds, J. T.; Luhitz, C. R.(Knolls .Itomic Power Lab., Schenectady, N. Y.); ltkln, I.; Harris,D. R. (Rcttis Atbmic Power Lab. [Pittsburgh, Pa.]). Aug. 17,1967. Contract W-31 -109 -eng-52. 22p. plus Charts. Dep.CFST1.

Evzluated libr~rles of cross sections were preparsd for naturalhafnlummd its isotopes ll~Hf, ‘TsHf, i71Hf, 118Hf, lTgHf, andlaOHf.The libraries contain total, elastic, capture, inelastic, (n,p), and(n,2n~ cross sections andelastlc scattering Legendremomentebelow 15 McV. The most recent experimental data were used intheeraiuation; rind, whenever data were not available, iheoret{calcalculations were made. (auth)

48416 (KrK-120(Pt.1)) NEUTRON CROSS SECTIONS FORFAST REACT03 MATERIALS. PART 1. EVALUATION.Schmidt, J. J. (Kernforschungezentrum, Karlsruhe (West Ger- ‘“many). Insti tut fuer Neutronenphysik und Reaktortechnlk). Feb.1966. , 1400p. (EANDc(E)+5-u(Pt.1 )).

A compreherwive documrntatlon and cr’ltical review of the avail-able rxperirhental and theoretical information on microscopic neu-tron cross nectlon data are presented, and the procedures that wereused ‘o rmiuce this information into cross section sets in graptti-cni and tabular form are described. ‘I’he neutron energies con-sidered range from 0.01 eV to 10 MeV, with emphaaia on faat _ -and resonance neutrons. The materiele ‘covered inciude C, Cr,He, H, Fe; bfb, Ni, O, 239X%,Na, ‘35U, and ‘MU. (D. C. W.)

.

24861 (WANL-TME-1721) A SIN(jLE LEVEL ANALYSIS ‘OF233u NEUTRON cRoss sEcTI~~, AN 33+‘23$fJMULTIGROUP

CROSS SECTION LRMURY. Bcimeider, M1 J. (WestingbcwseElectric Corp., Pittsburgh, Pa. Aatronuclear Lab.). Dec. 1967.Subcontract NP-1. 107p. Dep. CFSTI.

Total, capture, &d fission cross eecttona for n + ~U were ai-piltaoeously least aqusrea fit o,ver the ener@ range 0.4 to 61..4eV usfng t~e a ingIe-level Breit: Wigner formula. Sixty-three remnsncea were found to this range, Good agreement waa obtainedbetween fntegmf data and this fit to differential data for the reecJ-nance integrala of %. Resdnance parameter are gtven, alongwith brief statistical analyaea of them. A multlgroup croaa-aection llbrsry from .001 eV to 10 MeV ia presented. (auth)

24862 (WANL-TME-1746) CHANGES IN GAM AND TNSCROSS SECTION LfBRARfES: NEW ACTIVATION CROSS SEC.TIONS. Schneider, M. J. (Westinghouse Electric Corp., Pitt21-burgh, Pa. Aatronuclear Lab.). Jan. 1966. Sukontract NP-1.47P. Dep. CFSTI.

Some recent experimental data and evsluationa of activationcroaa aectiona for several nuclei are analyzed; and new GAM,TNS, and BLT Iibrariea txaed on these ansiysea are presented.The croaa aeotiona for the isotopes ‘tMo, i%, and %, and fornatuml Pb and Zr are amlyzed. A preliminary analysia of tbe%b(n,ti croao section ia ●iso aummarlzed. (D. C. W.) - ~

I

2. ENDF/B Tapes. ..

7689 fnAw-3151 23(u NEUTRON [email protected] DATAFOR THE ENDF/B. Wittko~f, W. A.; RoY, D. H.: Livo]si,h. i?, (Babcock and Wilcox Co., Lynchburg, Va,). May 1967.}04p. Dep. CFSTI.

Aa part of the coopcrntive effort of the Cross Section EvaluationWorking Group organized at 13rookhavcn NaiionaI Lai~oraiory inJune 1!366, the nuclear data on “% for uae in th’c Evnluatcd NuclearData Filc””B (ENDF/B) are fircsenicd. ‘The data cover the energyrange from 0.001 eV to IS MeV. Data aourc?etj are rcferenccd, mdthe theoretical methods used in evaluating certain data are de-scrlhed. A complctc lisiing of the data in the ENDF/B [ormat isprovlderf. (:tuth)

;~5;8 (1A–1152) NUCLEAR DATA FOR 240Pu. 2ti I%I. and. Yiftab, S.; Schmidt, J. J.; Caner, M.; Segevo M. (Israel

Atomic Energy Commiasimi, Yavne. Soreq ,Nuclear ResearchCenter), Dec. 1967. 100P. Dep.

An cvnluatlon of the baeic nuclear dats for 240Pu, ‘CIPU, andZttpu In the range 0.01 eV to 15 MeV waa made. Partial crof18P-II l,mR nrc cnnutructcd for the thermal and fan,t neutron rangea;

“ Ih( y arr pro~rntcd in graphic~i and tabular form. RceonanceI para mctcra and average psramete ra are recommended for the

r’eaonance region; they are presented in tabular form. The croaaaectiona constructed arc: total, nonelastic, eiaetic acattcrlng, ra-diatl! e capture, fission, total and partial inelaetic scattering,(n,2n), nnd (n,3n). Other nuclear &ta considered are: the averagepiameter~ above 1 keV, the average number of prompt neutronsper neutron-induced flasion, the average scattering coeine in tAeiab, system, and the energy spectrum of secondary neutrons fromfission. (auth)

55

.

.

.

.


3. Wide Ranges in Energy

1967

2Wbo (N4-1026) NfiUTRO NTOTALANf )Ait*-RtirlON ~CN(MS SECTlONS,OF ‘8Pu. Young, T. E.; Slmpmm, k’. B.; Ser-reth, J. R.; Cuops, M. S. (ldahu Nuclear flmp., binitu Falls).hler. 1967. Cuutrsct AT(10-1)-123O. 81P. flep. ~’F>Tl.

‘rhe neutron tutaf cross section of 2WPU wuu Ilwdborcitfrom ,0.00ti w G501JeV. Tlwtw (Lth givu niI@e-level Urctt-WtgnerPeranwterti fur rcqonancc# IJC1OW2tJ0 eV. The utmerw.1 ldafcross section at 2200 m/see is 588 barns. A value of 532 bsrrmwas cat cuirded for the effective (equivatcnt l/v) tfiermsl iibt@p-tion cross soctlon. Parameters of individual resonances below200 eV and average parameters at higher cnergiern KIVCa reso-:

. rmnce absorption integral of lW : 15 burns, and a v@ue uf 1.10 *0.20 X 10-4 for the s-wave neutron streirgth fuhctiun (1’~/Lt). (autit)

17341 (A ERE-M~1709) ETA AND “NEUTRON CROSS SEC-- ‘TIOf4S OF 2SSPUAND 2J3U. Brooks, F. D.: Jolly, J. E.: Schom-berg, M. G.; Sowerby, M. G. (Atomic Energy Research Estab-Ilshment, Harwell ( England)). Sept. i966, 18P, Dep. mn.

Measured values of q for ‘SSPU and ‘SU are given for the energyra c 0.04 to 11 eV, together with fission and total cross eecttons

Tfor a3U. Average values of. ~ were calculated and also, in the caeeof lSU, various ratios and integrals of the cross sectfonb and a forenergy groups of Interest for reacter design studies. Total cross-section measurements were also made for 2SSPUfrom 10 to 1000eV. Compxrlsons are included between the results obtained In theexperiment and those from other Iaboratorlea. (auth) .

.

25734 CONFIRMATORY EXPERIMENTAL DATA ON THE‘HARWELf4 BORON PILE V VALUES. Colvin, D. W.; Sowerby,M. G.; MacDonald, R. L (Atomic Energy Research Estsblifih-ment, Hanvell, Eng.)., Vienos, lnter~tionsl Atomic EnergyAgency, 1966, Preprint No. CN-23/33. 16P. (CONE -66iJ14-35), DTIE.

From IAEA Conference on Nuclear Data, Paria.The F values obtained by the Harweli boron pile experiment,

which have previously been repnrted (Symposium on the Physicsand Chemistry of Fissinn, Vol. II, p. 24, 1965), are approxlmitely2% lower than the valuea obtained wIth large liquid sc intillatoreand those derived from measured values of q and a. The valu? ofpiie efficiency used in thbse ml+asurements was obtained by usingthe associated particle technique, i.e., the d(y,n)p r~actlon. Twostandard neutron sw~rces, a ‘Ra-y-Be source and the AWRE ‘(oPuspontaneous fission ,source, have how been” c?alibrated at the Na-Iional phyy ical Lsbo rato’ry, Teddington, England, and in the b~mnpile. The count ratea of the-standard sources in the boron pile canbe used to obtain a second independent value of the plie efficiencyand hence give information on the correctness of the boron pd? Vvalues. The results of these measurements are given together withother information, which demonstrate that the correction proce-dures used in the boron pile experiment are valid: (auth)

.46722 (NAA-SR-12271 @U i.1)) NEUTRON CROSS SEC-

{frIONS FOR ~Pu, 242Pu, AND 4Cm. Supplement 1. Drmford,C. L.: Alter, H. (Atomic.v frrternationai, Canega P&k, Calif.).6ept. 15, 1967. Contract AT (04-3) -?01. 5p. Dep. CFSTI.

Seine corrections to the cross-section data for ‘itCm, z~gpu, andlQPU that were presented in NAA-SR-12271 are summarized.(D. C.W.)

‘17373 SUBBARRf’ER FISSION OF ‘2Th BY [email protected], S. B.; Kuznetsov, V. F.: Smirenkin, 0. N.Yadern. Fiz., 5: 257-63 (Feb. 1967). (In Russian).

The dependence of the reactiun cross sectibn un neutrun energywas measured in the region 0.6 to 3.0 MeV for the invetmgation of2S2~(n,f) fission near the threshold. Some characteristics Of thepotential barrier in the fissioh are discussed, in connection wilhthe reeulta of the experiment, The competition of inelastic neutronscattering to leveis of the 232Tb target in the energy region 0.75 to1.0 MeV abowa up cieariy in the cmurgy dependence of the fissioncross section. The disagreement between the kuown thernud neu-tron fission croae section 0.06 ● 0.02 nib and tho vniue extrapehitedfrom u, at higher energies ia ‘discussed. (auth)

57

196729970 (WANL-TML-1KM6) “A SINGIk LL”V~L”ANiLfSiS OFt~:fj ,\~E[f ON l{ECf;NT 0,, q, AND Uc hl~;tiU}{EMENIS; A n t2Jiu MuL’flGHCIUP CI{OSS SECI’1ON LI13RARY. Gibfwn, Gordon(Westinghouse Electric Corp., Pittsburgh, Pa. Astronuclea,r L*.).Mar. 1967. Contract SNP-L 143P. Dep. CFSTL

Total, capture, and fission neutron cross-section data for ‘SWwere simultaneously fit with a singie-levei Bre!t-Wigner ieaetsquare analysis.’ Two,’sets of resonance parameters for E <63

$e v ar presented. On$ set wa6 obt~n~~ when unit weighting wasused in the least-squares aneiysls, and another set was obtainedwhep w~lghting proportional to the inverse of the cross sectionwaa “used. \tl e resonnnce capture’ and flsnion lntegrais calculatedfrom the pa ,amcters agree in each case to within three percentwith ccrrcsfionding direct numertcal Integration of the data- TheeffcctM of simuitsneousiy fitting two cross sections at a time: totaland fission, and capiure and flasion were aiso s@tled. Two n +225” ~ui~groupcroa~Sectionlibrariea,thatdiffer onfy in the

resonmice range whd?e the two eeta of resonance parametersdeticril.wd above are used, were generated for use in reactor cai-culattons. The ratio of the capture resonan~e integral to the fla-a inn resonimce integral that is calculated (~ = O.51 ) with_eltherlibrary agrees with the reactor’ lntegrai measurement (IV= 0.50 *0,02), These iibrariee are presented. (auth)

. . . .17i50 (KFK-4&) T1iE FISSION CROSS-SEC;IONS OF SOMEPLtlTONiUM ISOTOPES IN THE NEUTRON ENERGY RANGE 5 ‘ITO 150 keV. Gilboy, W. B.; Knoll, G. (Kernforachungszentrum’,Karlaruhe (West Germany). )nstltut fuer Angewandte Kemphyslk).Oct. 1966. 12P. (CONF-661O14-43). Dep. mn.

From LAEA Conference on Nucicar Data, Parie, France.The neutron fiesion crose sectione of ‘JSPU and ‘40JW at 5 to ‘

Isn kcV were obtained by measurtng the 2BNZSU and 2’OPU/z%fftdon cross-scctton ratios. (D. C. W.)

42658 THE ENERGY DEPENDENCE iN THE RANGE 0.7TO 4 MeV OF THE NEUTRON FISSION CROSS SECTION OFzat~a GTarna, N.; Marlnescu, L.i Mlhai, I.; Petrascu, M.z2anduleaeu, A.; Voicuiescu, G. ffnst. of At022dC P12Ysics,Bucharest). Rev. Roum. Phyfa., 12: 43-51 0967).

The energy dependence of the fiwAon cross sec~ion of ‘soPuin tile energy range 0.7 to 4 MeV waa measuwd. The experi-mental polnta are compared with values calculated on the basisof many-level Interference theory. (auth)

.—, -

25517 (RFR-191) PAST ELASTIC AND INELASTIC CROSSSECTIONS FOR ‘~lU. Haggblom, H, (Aktieholaget Atomenergi,Stcckholm (Sweden)). May 3, 1962. 26p. Dep.

Fxperlmcntrd and semi-emplrfcai scattering croes sections for “2’nL’are compared with ihcoretfcai values [n the energy range 0.08to 6 Mc!’. The thcorctlcai cross sections are obtalncd by optical-modci calculations including apln-orbit interaction and by Hauser -Feshhach theory. Transport croes sections are, caicuiatcd bothfrom the cxpcr’tmental snd the theoretical differential cross sec-tions. Caicuiaiiona of Ineiastlc 1l-group crose sections are per-formed ueing the continuum mcdei fcr the compound nucleus inthe rcgfon shove 1.4 MCI’ anff asaumlng five excitation levels be-iow 1 McV. Between 1.0 and 1.4 Mev, the croae-e?ctions are ~b-tafncd by taking a mean value between the results from the con-tinuous and the discrete level theory. (auih)


I3. Wide Ranges in,Energy

35381 (AN I . 732b, jp 1fI-21 ~ Fl$SIOfi CROSi4-9ECTION ~EA-8fJREhtENTs OF t!~u, ~ h.f, Z$lsbi, ANIJ ~~lsh2IN TliE ENERf3YRANflE FROM 1 TO.25 keV. Jamml, G. fJ. (Aiomlo Ener~ Re-

-~~b ffctebllnbment. }iarvell (Engimsl)).. ..., -, . ..- . . . . . -- .. .

Fhaslon ‘rrons:srwtion mcasurrmcnts have been cnrrlmf out, hytlmo-nf-filghi cxpcrlmcnt, over the rncrgy rnn~c from I OV to25 kcv for the nuclhlcs 23311,2SSU,211Pu, nnd ~41PU. The dntn i)b-tnlnod from 1 kcV to 2S kdV nrc prcscntcd nnff comporcd with ex-ktln rlnta. R In shown thht In thla energy rangc,thc nvnllnljl(s dnta

f’fnr 2 ‘fJ nre In goud ngrremcnt nnd that the daia fnr ‘J3iJ and 2S9PUngrvo fairly WCII. A Itet of 19 rcfcrrnccs la Includcfi. kwth).

‘33953 (AAEC/ti166) A STUDY OF THE EFFECTfVERfI$ONANCE INTEGRAL AND DOPPLER COEFFICIENT OF?I:u, 222Th, AND ~@2PuUSfNG THE CODE COMPLEX LLIBRA.Keane, A.;- Kletzmayr, E. (Auatrnllan Atomic Energy Comm!a-slon Research Establishment, Lucas Hekhta). Dec. 1966.34P. Dep.

The cf fcctive retiommce inicgrai and Dcppla r cuef flcicnt of ‘W,222’f’h,~d 2401~ ~cr~ etudltid in dc~ail using thu I.LIIIRA complc!x Of

CCAS. Same cwrlicw rotmitti wrrd used for comp~rison to verifyihc validiiy of ilw LU 1111Arcsulis. Uscrqxwreic,s wrru cxpl:tim’d,and confidence cnn be placed in IIIC results glvcn by lhu I.UURACO(ICM. (mlth)

40432 . ‘TVASH-1074) REPORTS h THE ~EC NWCLEARCROSS SECTIONS ADVfSORY GROUP ME ETfNG, HELD ATBROOKHAVEN, NEW YORK, APRfL 13-14, 1967. Motz, H. T.(comp.) (European-Ameflcan Nuclear Data Comrnfttee). Con- otract W~’7405-eog-36. 153P. (EANDC(US)-99U: xNf3CfuB)-9u).

~. CFSTI.

● ✎ ✎

tiItii’iklM:238- neutron capture at 0.04 to 190 keV, radfative.wlttfhs for . . . . .

..*URANIUM-238- neutron finslon crose aect{on at 1 io 23 MeVURANRJM-23S— neutron flasion crona section et 2 to 21 MeV. . . . . . . . . . . . . .

● ☛☛

L .—.

25504 (EAtiDc~E)-.7;4 [tf)) NEUTRON cRw SECTION.9 ANDFlSS10f4 PA fl~hfETEIW OF 2!0Pu, 2(1h, ANf) 242fhI. p2XMdOCh’d.A. (Europca~ Atomic Energy COmm~itY, Geel (Beklum). Cen-

,trnl Nuclcsr Wmsurcmcnts Llurcau. Eurnpean-American Nuciear‘Data Comrulitcc.). Aug. 25.1960. iSp. DCP.

A,compilailon of mwtron rcsonrmcc integrals and parameter,vaiucs for the numbers of prompt neutrons emfttcd In neutronand spmtaheous fission, and neuiron fie$ion and totaf croee scc-tiona la presented for ““Pu, 2“ Pu. and “?Pu., (D. C. W.)

-w% - ‘( fA-1094) BASIC &.JCLEAR DATA FOR THE IJGHPLUTONIUhf lSO.TOpES. PART 1. CROSS SECTIONS. SCECV.M.: Caner. M,: Yiftah, S. (Israel Atomic Energy Commiaalon,

I Yavne. Scrm Nuclear Research Center). June1966. 27P.1 Dep. mn. -

Energy-dependent cross ‘scctlona of 24tPu, 24tPut and 241put In, the range from 1 kcv to 15 McV, are ccnstmct~ f~m tie ncant

avaliable experimental data by Interpolation, extrapolation, Ccnc!ralthcoretlcai argum.?nta nnd ayetemafics. The conatructrd crnaa

, s@ctions are prcscntcrt (22graphlcai fo~m in 14 fisurcs. (auth)

.

.

.

.

.

1967

21525 TOTAL “NEUTRON CROSS SECTION Ok ‘Pa., ”SImPson, F. B.; Coddlng, J. W. Jr, (Phllllps Petroleum Co., .I(fnho FalIs, Idaho). Nucl. SCI, Eng.,28: 133-8 (Apr. 1967). ,

Transmission measuremcnt~ on233pa were taken ~ith the Ma-terlals Testing Reactor (MTR) fast chopper. The total cross 8ec-.tionwns calcul~tcd Inthc energy range from 0.01 to lt3, dOOeV.These measurcmtmtq were made on700mg ofchemically separtidz~~pa in moxlde form. The protactlntum was produced by irra- !diatfng 280gof232Th lnthe Engfneerlng Test Reactor. The&amplerr-presented approximately 15,000 Ci of activity. The data weretnkcnwith aresolutlonof 0.08 to2. Opseclm. The Breit– Wign&resonance parameters were obtained for the resonances below18 eV. Theavcrage parametere@-ve avaiueof 0.75 x10-4 for thes-wave neutroh strength function r~/D. Weightitig the level epac-ings inversely a.42J +1 glvesthe average observed leveispaci~sperspin state of 1,1 Oand 1.84eV. Asecond-order poiynomidleast-squares flttothe uT@databetween O.O1 end O.10eVgtvesa220fJ rn/aec total neutron cross sectiotiof 55 *3 b, supersedinga value of 57 bgiven previously. The resonance-abeorption in-tegral forneutrons with energfes ahove O.4eVwa8caialatdtibe 901 +45 b. (auth)

.

12014 (iN-i015) TABuLAmoN OF. THE”TOTAL NKUTNONCRUSS SflC!Ti(JN OF 2SZU. Simpson, 0, D.; Muore, M. S.; fkrretb,J. ii, (Iduho Nuclear ,Corp., Idaho Falls), Dec. 1966. ContractAl[lfJ-1)-1230. 69P. Dep. mn. CFSTI $3.00 cy, $0.65 am.

Titu tolai neutron cross section of 2YZUwas mea~ured from O.(J1to 10,000 eV using the Mdtcrials Terntlng Reactur (MTH) fast chop-@r. A 2200 m,tcr/scc tutil nculruu cross bcctiun of 11j5 * 10b~ms was dcwrmintxf. Alululcvc.1 paranwturs MM lIs@f for reti-.onanccs below 30 eV. Resulla of the aulybIb iiuilcak that IWUfinnkm chnnncls arc nevdmf w d.uc ril,u the vkpet Imcntal tiara.A tahulntiun of Utti da% III Klvt!n. (awth)

42621 ToTAL NEUTRON CROSS SECTION OF 23ZU. Simp-son, O. D.; Moore, M. s.: f3erref& J.R. (Idaho Nucicar Corp.,Idaho Falls). Nucl. Sci. Eng., 29: 415-22 (Sept. 1967).

The neutron total cross section of 232uWSS measured from 0.01

to 10,000 eV using the Materials Testing Reactor (MTR) fastchopper. A 2200 m/eec total neutron cross section of 163 ● 10 bWaS determined. MuMievei parameters. are li~ted fOr resO~mcesbeiow 30 eV. Results of the analysis indicate that two fissionchannels are needed to describe the espetlrnen~i data. (autb)

. .._ ._

35457 (AEET-272) SELF-SHIELDED CROSS iJCT10N5 FORTHE MAIN FEffTILf3 AND Pi5tXLE NucLEI. Singh, R. Sbanker:Desal, G. A. (Atnmic Energy EstabllshmenL Trombay (lndla)). .1966. 18P. DeP.

%.lf-shlci’lwl cross-am-lions for lnTh, 2SW, 2SBU,nnd 23$%1whichoxhlhlt rrnon~n cr. lmhxvior in thclr rcnctl m croea -sc{,ll,m8 u Ithnrwtrnnp 31V ncrcssnry to rrprc8rmt the propr effcctlvr valuen bn multlgrmlll :mnivsls of rc*cture and to p,rrdlc! nrcurxtcl) Uw re-activity mwUlcicnts (!tte to tic DoppIer effect. etc. “rhcse wererwnlunlod from rewmmncc-tntegrul cniculntiona under the narrow-renonance npproximntion uainu the Inlcst avniiabie resonance pa-rnmctrrs at four tompnrnturca (300, 750, 1500, and 250@K) and ●tIJP(Potwtfal nmttnrfng ,srn88 soctlcnr per abmrrber ●tom) Value@ of

4u uml tiO Imrm for 1%1, UIId ~s~j ~,d 126, 21M, XJO, ud 40U IMruti

for ‘lSIJ and “bihI. ‘1’humtiLumof remmunce paramcteru fur hewselclt,efltb lrI UIMU,Iiticunbc.al tt~ ,{vIxI1 ltiuth)


3. Wide Ranges in Energy.

‘ 40457,. .-

CAPTURE CR”OSS SECTIONS OF ‘srNg. Shtpegta, ,Dotmid C.: Schmidt, Marcia: Keedy, Curtis R. (Argonne Na.ttonai Lab., Ill.). Nucl. Scl. Eng., 29! 218-19 (Aug. 1967).

Ncut ron ‘Ct4Phlre c mss sections of 2~~Npwere measured ateight neutron energies between 0.15 and 1.5 MeV. The experi-mental method was the activation technique in which the neptutum

“ 2arget was Irradiated with a mono energetic neutron beam and was, analyzed for the product 2MNp by gamma-ray epectrometry. (auth): .-.

42436 Tllf? FtSSION CROSS SECTfONS OF 1S3!J,134110‘$1;,22cu, ~~Np, 2t9Pu, l@pu, AND ~lPU RELATfvE TO THAT OF

~% FOR NEUTRONS IN THE ENERGY “RN”GE 1 TO 14 MeV.Whfb% p. H.: Warner, G. P, (Atomic Weapons If.tmearchEstablis@3ent, Aldermaaton, Eng). J. Nucl. Emtrgy, 21:671-9 (AuK. 196’7).

The fiaaion cross sections were measured reialive to the fla-sion cross section of ‘6U to an accuracy of approximately *27 atneutron energies of 1.0, 2.25, 5.4, and 14.1 Mc. V.Combinin these

fratios with {he known values of the fi~slon cro~s ~ectlon of MUleads to fission cross sections having an eelimated uncertainty of*3.5%, and which are mostly in agreement with other recent mea-surements. (auth) (UK)

1968

48423 (RPI-328-133, Pp 1-34) NEUTRON CROSS SEC-TIONS. (Rensselaer Poiytechnfc Inst., Troy, N. Y.).

The energy variation of F for 231Pu was measured in 4 over-lapping energy ranges from 0.01 eV to 10 kcV; spin aseignmcntsfor resonances nf 22 to 100 eV were made. The ahsorptlon andfi88inn cress sections of 2~gPuwere measured from 0.01 eV to30 kcV; a preliminary evacuation of the neutron capture-to-fissionratio was made for the energy range from 1 to 30 kcV. Simulta-neous capturr and transmission measurements were made forscpamted hf isotopes. Gamma pulse-height spectra from experi-ments with tbe 1.25-m iiquid scintillation capture detector are ‘presented for lSIAUand lSCW. The angular distributions of neu-trons scattered from resonances in Al weie measured In order todetermine the feasibility of thie approach to assigning spfns toI ~ O resonances, The technique of uafng ttle large liquid scintilla-tion detector as an anticoincidence mantie wae extended to fiseilec.icmente: preliminary scattering data for 23JPu are presented.(D. C. W.)

7892 (DPST-67-83-1O) USAEC-AECL COOPERATIVEPROGRAM MONTHLY PROGRESS REPORT, OCTOBER 1967.Ruache, B. C. fDu Pent de Nemours (E. I.) and Co., Aiken,S. C. Savannah River Lab.). Nov. 30, 1967. Conkact AT(07-2)-1. 5p.

Comparisons of values of q obtained from HAMMER caicuiationefor 2SSUand 23’%and experimentally obtained vaiucs arc made.

‘ Physics parameters for (l/q) (dq/dT) Iatticee are tabulated. Ef-fects of temperature variation sre outiincd. (M. L. S.)

59

1968

420?1 (RAI, -fr 21)) .\il;A$[lIIF. WKNT OF TflE RAIJIAI [VECAPTURE ANL2 f-lSSfUN C}{(M! SECTICfN RATIOS F(jf{ 2]SU AND2JtPu IN Tl;fi RF.Y>NA NCE-N KUTf\{JN ENEftOY REG1ON, RY~-

—.

h’. Yu. V.; Dcmsik, So} Chikov, N.: Yaneva, N. TrahaIa@d bySt (,1,hrn Amorett y (Hrookhavcn National Lab., Upton, N. Y.), fromAt. Uv?rg. (USSR), 24: 351~62(1966). 20p. Dep. FSTI.

fTime-of-fllght measurements of he neutron ftssi n cross sec-$tkrn!r and tho neutron capfurc-to-fi slon ratios crf 2JSPUand ‘MU

Nrrc made okor energy range? of 5 eV to 23 keV and of 0..15 OV to30 koV, rsspcctively. Capture and fission retronance Integralswere rrbtabrcd from the data. (D. C. W.)

5811 (EURFNR-400) ENERGY .4ND T?ShfPERATURE DfZ-PENDENT CAPTURE MEASUREMENTS BELOW 30 keV SUP-.PORTING DOPPLER EFFECT CALCULATIONS. Seufert, H.;Stegemann, D. (Kernforschungszentrum, Karlsruhe ‘(West Ger-many). lnetimt fuer Neutrbneqphysik und Reaktortechntk). Oct.1967. 25p. (EUR-3675e; KFK-631; CONF-67,1O43-1O). Dep.CFSTI. .,

Work performed under United States-Euratom Fast ReactorEkchange Program.

From Symposium on Fast Reactor Phyalcs and Relatkd SafetyProblems, Karlsruhe, Germany.

Energy- and temperature-dependent capture mea~remen~s below30 keV neutron energy were performed In natural uranium, tung-sten, and tantalum using the slowing down. tlow spcctromcttrr

-technique. ,’I%e.experimentaf actup us. d :or the exper’imcnts wm-siats of a iead block oi 1.3-m side lengti) containing two’ experi-mental chanhels of 10 x 10 cm? cross section. Into the firstchannel the target of a 14-Me V neutron generator iO introduce~,whereas the sticend channei is used for ineertion of the heatedrmmpiea. Pulses of 14-Me V neutrone having a puise width ofabout l/usec arc used. The neutron energy ie degraded fir~t byinci:t6tic colitsions; aftcrwurda nnly ciastic coillaiuna tukc piacoso that a apeci(ic rcdatiunship holds between mean neutron energyin thu lead pli~ and the timu after occurrtmcti of the pcutron puiao.fXIc to this time w-wrfgy rcluiion, n time tmdiysie procedure forthe dctcctur counts is appliMI. IJccauso thu energy range bciow3tJ kcV neutron cntirgy is most Intcrcstlng for Doppier-effectinvcsiigatiuns tho sio~ing-down-timo apectromcter ia ueed tomeasure the capture rat ioa of hot-to -coid aamploa of nfitural,uranium, tungatun, and tantalum. Thin eampies were heated todiffcmmt tcmpcraturca h- this purpose, and the capture y rayswere dcttictcd by propo”itlonaf ‘counters. Bt.icmme hot-to-coldcaptu t-e ratios are meaeurod the knowi,edgo of the nut ron fluxis nut n, , .~s.Iry; thercfortil a direct compuriaon of caicuiotcdand n,c.mul cd tcmpcrat uru-deixndent cross scclicww Iti posmiblc.A tht.orc.ticul anilyslti of tho exporimctdai duta for uraniuui lagiven. kmth) .


3. Wide Ranges In Energy

20572 (LA-DC-iZ!05) “ RELATIVE M5SIOf4 CROSS SI?CTIONSOF 23CU,‘ssU, 2a1Np, AND 23SU. Stein, W. E.; Smith, R. K.; Smith, .

H. L. (LXMAlamos Scientific Lab., N. Mex.). [1966]. Con-tract W-7405 -eng-36. 12P. (CONF-680307-24). Dep. CFSIT.

From 2nd Conference on Neutron C rosa Secttona,+ Tech-nology, Waabington, D. C. .

The fission cross-section rat!os 2MU@~U, ‘%~tUn and ~tNp/22Kuwere qeaEwcd witb,pukd, mormenergetic neutrons in theenergy range 1.0 to 5.0 MeV with time-of-ftigbt background dta-crimination., Vacudm evaporated fisaiie deposite (xO.5 mg/cml)were placed hack te back between two 9.5 cma surface barrierdetectors. Slow and fast output eignals were obtained simuita- “rreouely from each detector by means of acpara te electronic eya-tems. Slow, liocar pulsce which excccded a iower bound set toreject alpha particles were Identified as fission events. The .fraction of fragment pulaea below this blao, determined from anexkapolation of the pulse-height 6pectrtun, was -1.2%. Only thosefission evcnis which occurred during and a few oanoseconda afterthe neutron burst were recordod. Tbia time intervAl, determinedby the m aaured time resolution (1.3 nsec FWHfK) and the Ume

9walk of t e smallest ptdaeo (N2 nsec), wae typically 6 naec. F!a-aion eventa induc~d by scattered neutrona wbicb occur at latertimes were excluded. Characteristics of tht’a detector ayntem andpreliminary ,@fa were reported earlier. Present results includeadditional ddta on 2~8upJu and ~lNpflxU and new dam on ‘n UfllU,(auth)

18283 NEUTRON STfiNGTH FUNCTION MEASUREhl ENTSIN THE MEDlm AND HEAVT NUCLEI. Uttley, C. A.: New-etead, C. M.: Dimento K. M. (Atomic Energy Research Eatab- ‘lisbment, Hanveil, Eng.). pp 165-74 of Nuciear Data for Reao-tors. Vienna, International Atomic Energy Agency, 1967.

From IAEA Conference on Nuclear Data, ParirJ. See STi/PUB-140 (V01,1); CONF-661014-(VOl.1).

Neutron totni cross-acction measuremen~e were made ~iwecn100 eV and 1 MeV cn nuclei near the mans-100 and mass- 240 p-wave rcsonanccn us!ng the }farwell “bccater’t’ pulsrd neutronsource and ihc 1.20-m and 300-m npectromctcrn. TIW e. mventrcr@h. fupction B, and distant level parameter R- have u~uallr

been separately dciermincd at iowcr e&~iea ●nd the corrcsporrrf -{tw p-wave parameters arc obinincd from a Icaet - aquarrs fit toNC higher energy (>10 kov) totai croon section using the ●veragecolll.rion function expresoicrt from R-matrix theory. The d-wavestren~b function IS also determdcd uIIirrg plmmlbie ●aaumptlonaon the average parameicrs of the btgher artial wavea. The nu-clei Mudicd are 9~Nb, ‘Me, ‘wMo, ‘%UI, ?alTh, ZMu, 2SU, 131U,~lSSPU. (auth) . . ,

3529S (TPhf-RFR-682j 2$9Pu EVALUATIONS. W~l[n,‘Mnrie (Aktlelminget Atomenergt, [Stwdavik] (Sweden)). Dec. 7,1967. llD. Den.

The up&thtg of the Speng llbrnry for ‘$tPu to rcfkt recentmcasuremcnte and evnlunt!ons of the cross sccliona nnd reoo-nfulco pnramrtera for 2$Bpu iS rfi~cuaned. (D, C.\y. )

.

.

6cf

1968-29986 (ORN”L-TM~2140) MEASUREMENT OF THE tiZU-TRON FISSION AND CAPTURE CROSS SECTIONS FOR 2WJ INTHE ENERGY REGION 0.4 TO 2000 eV. Weston, Lo W.; Gwfn,R.; deSnussure, G. (Onk RldgeNational Lab., Term.); Fullwood,R. R.: Hockenhury, R. W. (Rensselaer Polytechnic Inst., Troy,N. Y.). Apr. 8, 1968. Contracts W-7405 -eng-26: AT(30-3)-328. 64P. Dep. C FSTf.

The neutron capture cross scctlon end flsalon cross section for2~u were meamrerf simulfaneeusly fh the neutron energy range0.4 to 2000 eV. A pulsed end collimated neutron beam was paseedthrough n ‘MU fieaion chamber placed at, the center Of a large liquidacintllintor. Cnpture and fission events in the % chamber weredetected in the acfotfllator by meana of their prompt gamma rays.Coincident signals from the fission chamber and liquid scintlUatordistingulahed fleaion from capture eventa. Comparisons with previously publlshcd data, using eimtlar and dtfferent rnethoda, aregiven. (autfr)

48s58 MEASUREMENT OF TRE NEUTRON FISSION ANDCAPTURE CROS9 SECTIONS FOR 233UIN THE ENERGY REGION0.4 TO 2000 eV. Weston, L. W. (Oak Ridge National Lab.,Term.); Gwin, R.; desauasure. G.; Fu~lwood, R. R.: Heckenhury,R. W. Nucl. Sci. Eng., 34: l-12(Oct. 1968).

The neutron capture crosg section and fiaslon cross sectionfor ‘W were measured simultaneously in the neutron energy range0,4 to 2000 eV, A pulsed and collimated neutron beam was paeaedthrough a 233Ufisainn chamber placed at the center of a largeliquid acintiiiator. Capture and fieeion events in the ‘SW chamberwere detected in Ure sclntiilatot hv means of their tmnmnt eammarays. Coincident eignaIs ~rom the-flsalon chamber-and iiq~idscirrtillator dlsttngulshed fission from capture events. compar~iwms with prrrl,wnly ~blished data, using similar and differentmethds, arc given. (auth)

3710 NEtfTRoN ToTAL AND .4BSORPT10N CROSS SEC-TIONS OF ‘S%. Ymmg, T. E. Odeho Nuclear Corp., Ideh?Falls); Slmpaon, F. B.; Berretb, J. R.; Coops, M. S. NucI. Set.EnK., 30 355-61(1967).

fic neutron tot~l cross section nf 2S8PUwas measured from 0.008tn 6s00 cV. These data give singie-level Brcjt-Wigner parametersfnr rcs,mances below 200 eV. The observed total cross sectfon at2200 m/see is 586 b. A value of 532 b wae calculated for the effec-tive (equivnlcnt I/v) thermal absorption croeg eeotion. Parameterof individual rcsonancea below 200 eV and average parameter at

: higher energies give a regonsnce aba’orption integral. of 164 ● 15 b.and a value of (1.10 * 0.20) x 10-4 fer the a-wave neutron strengthfunction (~#/D). (auth)

.37341 (IN-1132) NEUTRON TOTAL AND ABSORPTIONCROSS SECTfONS 0F,242Pu. ~oung, T. E.; Reeder, S. D. (IdairoNuclear Corp., Idaho Falle). Junq 1966. Cohtract AT(10-1)- I1230. 85P. Dep. CFSTI.

The t~al neutron cross section of 242Pu was mensured from0.008 to 8000 ev using PUC+ powder anrnplcs ,in the Materiala, ‘Tcating Reactor (MTR) fast choppqr. The data were analyzed tngive the thermal absorption cross eectlon nnd resonance peram-etere below 180 eV. The obacrved totai neutron croes sectionat 0.0253 eV ia 39 * 1 b, and tbe effecUve (equivalent I/v) thermalab80rptinn croaa eection derived from the meaauremcnt is 22 +2b. Parameter of individual resonances bclnw 180 eV and averagepzrametere. at higher energiee give a reaomnce abeorptlnn~nte-‘Rret of 1090 * 60 b and a neutron a-wave stretutth fonctfon.fr#/D)if (0.9S ● 0.1 fl)l 0-4(eV)-K. (auth)


3. Wide Ranges in Energy35650 MEASUftEMENT OF THE ii FYECTiVE CAPTURE-TO-FISS1ON RATIO IN 2S9PUAND 2~SUIN TWO DIF’FEitiiNT FA>l NE-ACTOR SPECTRA. Andersaon, T. L.; Helletrnnd, E.; Hukansson,R.; Bajbor, Z. (AB Atomenergi, Studsvik, Sweden). pp 17 i -ti~ ofFast Reactor Physics. Vol. 11. Vienna, international AtomicEnergy Agency, 1966.

From Symposium on Fast Reactor Phyaica and Rcdatod safetyProblems, Karlsruhe, Germany. Soe STI/PUB-165(1’&’2);CON F-6~1013-(VOl.Z).

lntrgrnl valurs of o for 9~U and 21qPu hive bern drwlucwl fromcxfw! {mwts In IWOtilffrrtmt mm-s (me(f Inn 21SUflflsion rnrrsy50 nnd 1S0 Iwf’. r’espcctivrly) in the FRO reactor, Tho mr.thed ofmensurcmcnt Is the Fnmc ns that uacrf for Instance at ZE f3HA.The rxprrimcnt Includyfl rcnct{vit.v IOcWeUrCI’nC12teOf tllc anmPlemnterinl ,mwfof n stnndard, IOB, ns wll IIS,nn nheclutr determina-tion of the fitmi,on rtttc In ‘lSPU hnd 13SUantf the capture rate in l“B.The cxperimrmtal o vnlum agree wc~i with the cnlculatcd ones forthe hard eprclrum core roeaeuremente, ,both for 2SSUand 23qPu.The mcnsur.crf value for 71’Pu In the soft c~re is eiightly higherthan the calculated oric. The discrepancy for 23WfIS large andhitherto unmplalncd. (nuifd

33086 (ANL-7310, pp 431-511) REACTOR COMPUTATION .METIfoIX+ ANfI T[lfIUf{Y. (Argonne Natlormi Lab., 111.).

● .9

URANIUM- noutrrm cross ecctirqrs for, crvstaflinc rf!ects MID{,p;,lrr-brnllrlrnc ff; rruommc~ Integraln for, rrystallfne ●f-fcctn m (M. L. S.)

54)s05 ANALYSIS IN TERMS OF A GENERALIZED OPTICALMODEL, OF TN E CROSS SECTION OF ‘8U IN THE ENERGYINTERVAL (0.05 TO 15) MeV. Balddni, Brunn: Saruie, AnnaMaria (C’NEN, Bologna). pp 741-50 of Fisica del Reattore.Rome, Consiglio Nazionale deiie Ricerche, 1966. (In Italian).

From Conference on P,hyaice of Reacto;e, Milan. See CONF-469.

‘Uac of a generalized optical model for analys!e of f$c 1S8UcroesScctlon IS dc’scribed. Illffrrenilal crrrsa sectlnrm are Khown forE = 0.650 McV, 1.1 McV, 2.5 McV, 4.1 McV, 7.o McV. and 14.1McV. The rquntlmrK uried for the analyels are glvcn, Totsl anddifferentlnl Inelnstlc cross eectione Arc shown. Behavior of theI,cgrndre polynomial exfrmrainn coefficient tb determined as sfunction of cmergy. (M. 1..S.)

35542 INACCURACIES IN TIfE CHAffACTER[STfC PARAM-ETERS OF A FAST POWER f?iiACTOR I)IIE TO TIIE PRk;VAIL-ING UNCERTAINTIES IN THE f3ASIC NE(jTRON DATA. THEIRftVAI,UATION AND THE EXTF;NT TO WHICH THEY CAN f3E RE-DUCEI.) DY CRITfCAL EXPERIhlENTS. ffsrre, J. Y.; Ravlcr, f.(CEA, Cridarnchc, Frnnce). pp 20S-23 of Fast Reactor phyei~.vol. 1. Vicnnn, Internntlonnl Atomic Energy Agency, 1968. (InFrench).

From Symposium on ,F’eet Reactn~ Physics and ReIated Saf~i‘Problcm3, Kariaruhe, Germany. See STI/ PUB-165(VOL1);

, CON F-671 O43-[VO1.1).The innccurmcice M the chnracterfstlc parameter of a fact

rwwtor due to unccr~~lntlce In the basic neutron ciata, using a .~cncrnl!zcd perturbation method are dcscrlfmd. The rwmits of “ “crltlcnl exp~rlmcnte to lmprov~ the accuracy of the calculated

. krrmnete and lhcrcby poaalbly improve the crose eections Urem-sc]ves are preecnted. (auttO ,’

61

1968

S0598 (LA4527) NEUTRON CROSS SECTIONS FOR 21%AND % IN THE ENERGY RANGE 1 keV TO 14 MeV. Berlljn,J.-J. H.; Hunter, R. E.; ‘Cremero C. C. (Los Alamos SblentiffcLab., N. Mex.). Aug. 1968. Contrnct W-7405 -eng-36. 33P.DeP. CFSTT.

Recommended cross sections for 22tu and 238u are preeented.

Comparisons of calculated an~ experimental values of Integralsye.tcms were, utmd as a guide in ChW8ing the fltd to’ microscopiccross -.ecction data. (auti)

3s333 ME ASUNNO’THE RELATIVE INTENSITY OF FI.WONREACTIONS. Bondarenko, V. V.; Buehuev, A. V.: Vorepaev, A. 1.;Zbzov’eT, V. P.; Ukratntbev, F. I.: Yurova, L. N. At. khterg.(USSfl), 24t fi2-4(Jan. 1966), (ln Ruealen).

In oMatrttog information 9n tbe ●~ce-energy diatributton of

neutrons in a rractor, the distributions of fission intensiUee ofdiffc rent iaotopcs are measured ztt various points with fiaaionchambers or by an acUvatIon met$od. A series of rheasuremcntewrrr made on n fast neutron aescmbiy coi_d@d@’ rods filled withcnricht’d uranium. Small fission chambers (8 mm In diameter●zd 40 mm in hcl~ht). and nstur~ and 9~ uranium foils wereused in thr mrssuremrnts. The fiaeion product acUvity in thefoils was mrasurcmt’nta. The fitmion product activity in the foilswas mraaurrd on a Nal(Ti) counter. An emaly$ls of. the cxpcri-mcntaf reatdts shnwcd that Inhomogeneitics due to the hcte,z+ogn-ncity 0[ Uw Ixttlcc were observed “in the spsce-energy distributionof neutrons, The neutron i!pectra in the channels and in thespaces Izetwrrn the cbamels dlffcred. conaidcrably: T%e‘hctero- ,grnclty of tire systcm had im effect on the 2*U fisslnn reaction,but not on the aSU fission reaction. BOUI the ftssion chamber asdfoil activation mdizods were free of systematic” errora 8s shownby cxpertmenta in a homogetteoua regton. (TTT)

16053 lNT~GRAL ANb DfFFERENTIA1. CROSS SECTIONS ,OF 32Th F1ssION By NEUTRONSO Er,nag,im~~vO & B.;

Smirenidna, L. D,; Smirenkin, G. N. 18P. (In Russian).. (CONF-661O14-51). DTIE.

Fr.m IAEA Conference on Nuclear Data, ParId.The energy dependence of the fission cross section ai(&) uouslly

shuwti a comI~lex rntructure in ndd [lssionable nuclei near thethrez.dwid. Cimrae.tcrlstlcs of the l,,wur flsslon chwzneis can bederived by rumparmg Uw o~borvcd fisslun (.ross aectlop U*and theanguiar dlatritmtlom 0[ the Ilbslon products with the thcoretlc:dvulue~. Then the chxracleris tics of ttw lower fiusion chanucis aretmlectcd In sucia a way us tn obtain agreement between the calcu-Intcd mrd experimental values. Such m smdyais led to the follow-ing succession of lower channels of the transitory 2s3rh nuciuua,which were excited In the 2=Th (n, o reaction by neutrons having atienor~ I& <1.8 MeV: ~z+, 7,-, and ?’2’. The new cimnnels NithK = /2 explaln the Inflexlon of Uf in the region of ueutrcm energy~ z 1.1 MeV, (Tf7T)


3. Wide Ranges in Energy

18250 RECOMMENDED VALUES FOR THE NUMBER OFNEUTRONS PER FISSION. Fillmore, F. L. (Atomin h_zterna-Uonal, Canoga Park, CalU.). J. NUCL fAzergy, 22: ‘79-97(Feb.1968).

o

The avallahie cxperimtmlal data for the value of v fur fiasileand fcrtllo Isutopcti are reviewed. Tho atnmluto dotormination

I of u for ‘t2Cf IMdizwusw-i, ~ineo this providw thu etaruiard fornorm.aflzing the other values. Bawl on wclghtcd avera~oti of theexpcrlnwn:ai datzz, rwxmmcndd 2200 m/8cc valuee aro pre-sented for 23$U,23JU, 2]4Pu turd 241Pu. Tile avnihbio dntn roiathzgtbe depwzduzco of v on Incidcmt neutrwz energy arc tabuiatcd, md

. . .. ●tralghtline fits to the data ●re m~e” by the method of least

squares. These renulte ●re uf direct value in reset.m calculat(msand the re18ted evaluation of nuclear cross Bastions. Althoughthere are inatzmces where the data tndicate structure of a morecomplicated nature, no ●ttempt ia made to analyze tbe8e attuatlons.For practicel pmpnses, a reasonably satisfactory fit to the datacan be made with not more thaa two strafght lf~es. (suth) (UK)

33014 THE HfGH-ENERGY INfSLASTfC SCATTERING ANDWE EARLY NEuTRON DECAY IN ~WJ ASSEMBLIES. GOZd,,, . .T’ea’ti~ d’l)uttremont, P. (Gulf C@z&al Atomic Inc.. San Dfe$.,,

! CalIf.). Trana. Amer. Nucl. Sot., 11: 292-3 (Juse 1968).From l-tth Annual Meeting of the American Nuclear Soeiely,

Turwzto. Seb CONF-6S0601.. .

~ 50599 . (LA452s)’ NEUTRON cR&4.sEcTf0t4S FoR 2%2AND 240Pu IN THE ENERGY RANGE 1 keV TO 14 MeV. Hunter,R, E.; Bertfjn, J.-J. H.; Cremer, C. C. (LOIJ Al~os SclentlfloLab., N. Mex.). July 1968. Contraot W-7405 -eng-36. 27P.DeP. CFST1.

Recommended crose sections for ‘otpu and ‘tapu are presented.Comparisons of calculated and experimental values of integralsystems were ueed as a guide in chooalng the fits to mfcroacopiccross -section data. (auth)

‘ 32597 RESONANCE PARAMETERS OF ‘“Pu. PART I.- NEUTRON WIDT~S. KoIar, W.; poeckbof.f, K. H. (E URATOM,

Geel, Betg.). J. Nucl. Energy, 22: 299-315(May 1968).The neutron total crose section nf 2?Pu waa measured with htgh

resolution br the energy range 20 eV tn 5.7 keV. Up to this energy,264 retxmancea were detected and analyzed with respect to rm usingthe area program of Atta and ilarvey. For 32 resonances between38 and 820 eV, the full sot of rcsonan$e parameters E,, r. and I’7could bo evaluated by coinbinlng the ro.vultn nf the trnnsmlnsinn ex-periment wtth thnso O( tho capture oxpcrimcnt dcscrilwd in Pert U.For tho 102 rcmwmnccs up 10 151)(1cV, & mean Imw-1*ptclng of ~ =14.7 t 0.8 t.V was oljlaincd. On the amw!mplion that all rc.snnanceoin th~t rnngo aro of the s-type, thw strength fum”tinn yivlds So =1.05 + 0.16 x 10 4. (auth)

62

.

1968

37373 ABSOLUTE RADIATIVE CA PTURE CROSS SECTIONFOR FAST NEUTRONS IN 2S8U. Menlove, H. O.; Poenftz, W. p,(Kernforschungszentmm, KarImtshe, Ger.). Nucl. S& Eng., 33:24-30(1968).

The capture cross section of Z$OUwas mensured ahsolutcly ata neutron energy of 30 keV using klncmatically collimated neu-trone from the lLl(p, n)7Be reaction near threshold. Actlvatlontechniques were used to determine both the number of captureevcnte and the number of neutrone that eccurred during the ir-radiation. The result of the 220Ucapture cross section measure-ment Is 479 + 14 mb at 30 keV. In addition, the shape of the ‘8Ucapture c’rose section WZEmeasured for noutr.on energies from25 to 500 keV using neutrone from the 1Lt(p,n)7Be reaction. Thecapture reactions In the 2$SUtarget were detected ualng a largeliquid acintlllntor tank and time-of-f llght techniques. The relativeneutron flux was meapured using a flat response neutron detector,The croea-section shape measurement wna normalized to thepreeent abaolute measurement at 30 keV. The present measure-ment was compared with eeveral meaaured values, theoreticalcalculation, and compiled values of the ‘$aLfcapture CI oss aec-tIon as given by other authors. (auth)

32621 RATIOS OF F&ST NEUTRON F1iSION CROSS SEC-TiONS OF ‘afJo 2SSU,AND ‘SPU. Ncaterov, V. G.; Smiretin,0, N. At. Energ. (USSR), 24: 185-7 (Feb. 1968). (In Russlaa).

Relative fission cross scctlone of U3/u~ (2%J to 23SU)and ofU#O (z~spu to 23SU)were determined over a neutron enc~y E

%of O. to 2.5 MeV at a relative accuracy,of 1 to 2% by measuringthe number of fieslona in a double ionization chamber contain-ing layers of the isotopes which were to be compared. Since th6fission cross acction for the 23SUisotope la well known with a high

‘accuracy of 2.5 to 3% at higher neutron energlee, it becomes poa -slblc to derive more accurato data on the croea sections of 233Uand ‘39Pu. The rt!euita were compared with the data compiled byDavey, and it waa found that the two sets of data were in goodagreement at En <0.7 McV, but devfatcd from each, other by 7 to10’%at higher values of &. The reeuita are fn good agreementwith the data of I~mpilere. (TTT)

.


3. Wide Ranges in Energy39651 INVESTIGATION OF SPACE-DEPENDENT FAST FIS-SION RATIOS AND MEASUREMENTS OF FISSION-FRAGMENT RE-COIL RANGES IN ALUMiNUM. OaiaB, David Justin. Ithaca,N. Y., Cornell Wniv., 1967. 147p.

Thesis.Space-dependent valw-a of ~28 ~S8U to 31SUfiaalon ratio) are

mcnsurcd in two cores of the 2. i% enriched U02, light watermederated critical fncillty at Cornell University. Measurementarc alao mnde in un ieoiated 0.600-in.-diamctcr fuel re.i in apurely thermal flux. Hefcrogcncoue finite lattice caiculationeare made with dlffcrcnt cross section ecta to investigate croaaacctlon uncertainties. The ‘MU croea eeotion8 rccommcnried hythe Atnmlc Weapons Heecarch Jlatabliahmcnt produce agreementof ~e calcul~timse with the meaeurcment of 628 in a single fuci ,rod (628= 0.0150 i .0003), and bccatiee Uincl ha~ little effect ~nthie calculated vaiue, the agreement indicates an integral accu-racy for U( of about 2%, “which la the accuracy of the isolated rodexperiment. For tic finite lattice calculations, the core regionis taken to be a homogenized cylinder with the space-depchdentfact flux at each ~f 30 energy pointe approximated by a fourth-ordcr even polynomiaf,l ueing the neutron transpert method ofK. B, Cndy and M. Ciark,, .Jr. TWO formulas for correcting ,anleotropic scattering result in’ high and low limits for 638. Kn-ergy-dependent disadvantage factors for the 30 energy points,used for obtaining homogenized cross acctione, are obtained froma multi-energy escape probability c~lcuiations for the infinite iat-ticc CCII. The cnlctilatcd intcnalvc (Infinltc lattice) values of 628 .arc eubstaniiaily higher (abut 15% to 2U) than the extenelvevaluca calculated for the finite Iatticca, showing a significantleakage effect. Tho two experimental ~inte for the 1:5/1 cureeuggcst IAat the’ average u, rccommcndcd by AWRE is accurateto about 2’M. For the 3/1 core, the theory and experiment (about‘1’%e!qwrimcnicd error) show a smafi unexplained discrepancy.The asaumcd utsccrtainty of UI..I and other croae sections (6b-tained by subjcctivciy aurve$ing experimental data, for crogesections) is not large etiough to account for the 3 to 42 discrep-ancy. The experimental data are obtained by using a lithium-drifted germanium detector t? measure the activities of the 1.6-MeV 140La photopeak in highly depleted (23 pphi 33SU)and in 2.1’%enriched U03 w~fcre. The prccieidn of thie method ia believedto Lx better than that ohtaincd from tireshoid aroma-ray counting, .

fpartly becauae no mcaeurcmcnt with a double iea]on chamber ofthe time-dependent ratio of 2~u to 33$Ufission product activitiesis needed. There ia, however, a systematic uncertainty of abuut ,i2$iJ in the l@La yieirl from fission of 2PnU, and this Z% must beadded to the Wandard crrom quoted here for the 628 measurements.A study is made of the grose fi’eaion product gamma-ray spectrumto discover any better mcane of mcasuting fiesion evente. None

,is found, but it ia discovered that gamma-ray spectra from thegermanium detector can ix? used for quantitative measuremcntaof many fission produclg with no chemical separations. A icch-niquc for computerized evaluation of compicx gamma-ray spectra

, ie developed. By using the computer program to analyze the spec-tra obtained with Uw germanium deiecior, mettsus-emcnta aremade of tbc mean recoil ranges in afuminum of 19 high yicidfiaeion fragmenta from ihcrmsl fiesi’on of 21SU. Rangea are cal-cljl:tlcd iroln tkc rclatlvc numbcr~ c~ffission frngments siojqdngin crick of four nlumlnum caichcr foils (1,204 mKicm3) placednext to n Ihl!j flinl of 33$(!. Prt.risif)n var[f,s from 11.2to i.!j’~,With most m+aatiremcnts having standard dvviatione between0.3 asni O.WL. Prvvious oxlwrimcntc.rs rclmri comparahic nccu-rllcy. Ilowc’ver, tho prcm, nt rxpciriment involve. s loss of f,, rt, andprovirtca rn~r.w ior mnny niomic mnsmm which hod not been mea-surcfi prcvi(n]rnly, (Ixs8. AhMlr. )

63

1968

i8106 NEUTRON CROSS-SECTION EtiALuAnoNs: PAST,PRESENT, AND FUTURE. Parker,K. (Atomic Weapons Re-search Establishment, Aldermaet.on, Eng.); Goldman, D. T:;WIIlltn, L. .pp 293-307 of Nuclem Data for Rambrm vi-q.International Atomic Energy Agency, 196’7.

Frem IAEA Caiferonce On Nuclear Data, Paris. see S~/PuB-140(V01.2): CONF-661014-JV01 .Z).

The need and requirements for cros6-necClon evaluations is dts-cussed; and the evahmtlone that weke available on June 1, 1966,are reviewed. (D. C. W.)

36s7 (EURFNR-404) SOME NEW MEASUREMENTS ANDI7EXORMAL1ZATIONS OF NEUTRON CAPTURE CROSS SECTIONDATA IN THE keV ENERGY RANGE. Poenttz, W. P.: Kompa, D.;Menlwe, H. O.; Beckurts, K. Ii. (Kernforochungszentrum,.Karlaruhe (West Germany). Institut fuer-Angewandt~ ~crnphyalk).Oct. 1967. 14P. (EUR-3679e: KFK-635: CONF-671O43-9). Dep.CFSTI.


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.

Work performed under United States-Eurat,om Fast Reactor \Exchango Progrnm.

From Sympotdum on Fast Reactor Phyelce and Related Safety “ProbIems, Karleruhe, Germany.

T}IOnbsolute neutron capturn cross eectlon of Au was measuredfor neutron cncrgtca of 25 to 500 keV to am accuracy of about +s!6.Absolute normalization of tho relative crose-section curve waaperformcrl at a pcutron energy of 30 keV. The capture cross sec-Uon of 23% was rncasured over the same energy range. The cap-ture cross ticctlons, rclatlve to Au, of a number of mcdlu~-weightand heavy nuclldes were meaaured, using a Ume-of-ftlght methodand n large liquid eclntillator tank, in the energy range from 10 to150 keV. Evaluated data are presented for Cs, Hf, Mo, Nb, Re, Ta,and W. Tbe implications of the new data for fast reactor calcula-tion were studied. (D.C. W.)

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64

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4. Capture-To-Fission Ratios

1967

42610

TIvF: To 2S$-1060) - IETA RATfOSOF UiPUAND241PURELA-’

. Fast, E.: Aber, E. F. (Idaho Nuclear Corp.,Mnho F:ills). Aug. 1967. Contract AT(10-1)-1230. 42p.fkp. chsm.

“rhe rn!loaofthcneutron rcproducNon conshnter f(Pu-239)/~([!-235] nndq(Pu-241)/q( U-23 S)wcrc. dctcrmlncd [rem rcac-tidtymcwwlrrments in ARMFLI nnd ARM F-11. ftcaulta for22f)fl ‘m.sm- nnd Mnxwclllan av-rage VIIIUCSare given. (truth)

38320 MEASUhEM”ENT’OF ‘SSUALPNA IN AN fNTERMEDl-ATE-ENERGY NEUTRON SPECTRUM. Fox, W.iQ.; Klnchfn,G. H.; Smders,J. E. ‘(united ICfngdom Atomtc Energy Authority.Winfkith, Eng.), Trans. Amer. Nuc1. *c., 10: 231 (June 1967).

From 13th Annual Meeting of the American Nuciesr Society,San Diego, Cslff., June 11-15, 1967. See CONF-6?0602. .

42616 G9APD-TM-625) MEASUREMENT .OF CHANGE INa AND FISS1ON RATE WfTH TEMPERATURE FOR 1% (LWB -LSBR DEVELOPMENT PROGRAM). Green, L. (Rett18 Atomicpower Lab., Pittsburgh, Pa.). Aug. 1967. Contract AT(l I-1)-Gen-14. 21P. Dep. ~FSTI.

\The Doppler effect of en enriched (93.2%) U02 target in a l/E “.incident neutron spectrum was Investigated in nbeam geometry.The fission and capiure rate~ of the target, encioeed in a quartzgiaeE furnace, wera foliowed by meane 9f two scintillation count kIIoperating a crossover-pickoff coincidence eyetep. Analysis. of 2.time data yieide change in o, ihe capture te ~iesion ratio, and inthe fieei.on tntegraf, se a function of temperature. A eingle target0.090-inch thick wae studied in the range from mem temperatureto 800’C. Experimental concluaione obtqlned were the capture tafission ratio, a, increased with temperature, and within a 2%uncerhinty no change waa observed in Ure fission rate ovkr thetemperature intervai studied. Monte Cario calculations ueingrecent re80nance data wdre performed for the conditions of theemriment and agreement was obtsined with ~ese conclusions.(auth )

4434 (fDCLi4678) fMJRt4UP DETERMINATION OF NU-CLEAR FUELS. Project Re~rt for the Quarter January l–March 31, 1966. Maeck, William J.: Lieman, Frederick L.;Rein, James E. (cds.)’ (Phillips Petroleum Co., Idaho Faiie,[dafrn. Atomic Energy Div.). Oct. 1966. Contract AT(lO-l)-20S. 23p. Dep. mn. CFST1 $3.00 cy, $0.66 mn.

Measurements were msde of the a (capfure-to-fkmlon ratio)for U-233 and U-235. ‘fWOcapsulee cnntainbrg a kriown amounfof hlfily enrlchcd U-235 and four catmules containimr a knownamc&t-of highly enriched U-233 we~e irradiated in ;he MTR andsubsequently analyzed for fetid and isotopic uranium concentra-tion. Based en these data, fenfatIve effective ~ values (at a Cdrat:o for Co * )5) and tie computed 2200 m/net valuea are: ‘0.0997 ● 0.00

#and 0.0964 * 0,0016 for U-233, and 0.1768 * 0.0016

,, 0.1716 * .0015 for U-235, ?eepectively. (auth)

46952 ATOM RA’f’iOS AND EFFECTIVE CROSS-$ ECTIONR.4T10S IN HiGHLY DEPLETED PLU.TONiUM-ALUhllNUMALLOY FUEL. Reardon,, W. A.; Christensen, D. ~. (PnCificNorthweet Lab., Richlnud, Wash,). Contract AT(45-1)-lS30.NucI. SCi, Eng., 30: 222-32(1967), (BNWL-SA-5581.

The graded exposure of 4 Pu-AI aiioy, i 9-ted cluster,d fueielements, and the subsequent destructive sampiing of the vlementshave provided cxperimentni data showing thv variation of IW iso-topca with irradiation. Irradinticpa wure conductixl in the heavy -water-moderated ami -cooicd Plutonium i{ccycit, ‘i (,st itcactor.Using ‘SICSSas u fission indicator, tbe depietion of !hv uutlui Pu to50.4 * l.i’~ ia deler!pined. iieacior effcwttve cross -scctlun rtitlosfor the Pu isotopt,s sre dvrlvcd from the duta, ami rcsuits show

thut the cupture-to-fiaaion cro~e-section ra.tw ior 23SPu@~-1 is0.426 ● 0.019. (auth)

Neutron Cross Sections:1967 11968 4. Capture-To-Fission Ratios.-

12248 DDtECTDETERMfNATION OF2sSUCAPTURE-TGFISSION RAT~O IN A ZERO-POWER REACTOR. R@marr, W. C.;

‘ Bre@cber, M.’M. (Arzmme National hb~, nl,): Nucl. %1. Eng.,27: 34-44 (Jan. 1967).

An experimental method for the ‘deterghsation of the spectral *average of the capture -to-f isaion ratio a for materials insertedin a Iow-flux reacto’r la described. The procedure involves a com-parison of reactor response to oscillated samples of a fiasilematerial, an absorber, and a spontaneous fission neutron source,nius an emerimental determination of fission rate for the fissile- –..mate rial ~nd capture rate for the absorber. In addition, it ia nec -eaaary that tbe neutren source be calibrated. These experimentalresults, combined with a knowledge of the number of neutrons pe_rfission for the fia.eile inaterial, yield a value of the quantity 1 + a.This. method has been tested in Hi-C Core’ 10, a cr!tical aeaemblyof 3%-enriched-U02 fuel pins, moderated end refiectcd by lightwater, in a lattice spacing which yields a H-to-nSU atom ratio of2:91. The oscillator and absolute counting data ield a value of

r0.217 for the central capture-to-fission ratio of ‘%, with nstandard deviation of *0.015. Thie agrees well with values de-rived from a combination of measured ‘% fissien cadmiumratios and calculated thermal and epithermal valuea for a. (auth)

35650 MEASUiWMENT OF THE EFFECTIVE CA fiURE+TO-FISSION RATIO IN 2SjPo AND 21SUIN TWO DfFFtiREN ~ FAST RE-

.

ACTOR SPt’.CTRA. Anderanon, T. L.; Hellntrnnd. k:.: Ilakam.son.R.; Qajtror, Z. (AB Atqmanergt, Studstitq Swodon). PP 171-S5 ofFaret Reactor Physics. Vol. II. Vienna. lntOrn~tiOn~l AtomioEnergy Agnncy, 1968.

From Symposium on FmN Reao~r Pbyelce ●nd Rel~ted Safety’Problems, Ksrlm’uhe, Oermany. See ST2/PU&166(Vol.2)tCONF-671043-IV01 .2). .

23~u-●nd ZJipU-~V~ bc& &du&f froIIl .0Integral values of a fnr.exportments in two different coree (median 21SUffsston energy

● <

60 and 160 keV, respectively) in the FRO reactor. The method ofrnensurement 10 the same as that used for ihstmrce at ZEBRA, ‘The e.xperimwrt lncltalcs reactivity meneuremcnte of the namplematerial and of a standard leR, ne well ss an nbtsclute determina-tion “f t~ fission ~te in d~pu and 235u ad tie cnptire Mtc in IOB.

The experimental a values agree well wtth the calculated onen forthe hard spectrum core measurements, both for ~~iU and 2’ePu.The meaaured vaIue for 21ePu in the soft core in slightly higher

! than the calculated one. T’he discrepancy for 21SUis large andhitherto Urscxplafned. (auib) ..- .

-—. — .. ----io420 (AEEW-1{-526) MEASUREMENTS AND CALC~LA-TIONS OF RATIOS OF EFFECTIVE FISS1ON CHOSE SECTIONS INTHE ZERO-POWER FAST REACTOR. ZEBRA. Stevenson, J. M.;;

, Breemfield, A. ?T1. (Atomio Energy Establishment, Winfrith (En-~land)). June 1967. 22p. ~p. CFSTI. UK 4d. Od.

l%r comp.nri90n of mcasurod and cniculatcd central fiseion “ :‘mt Ios pro~idtw a useful method for checking tho accumc y ofmiculntcd spectra and fisdion cipsa-section data. A set ofp?raiiel plate fission chambers was specially made for Zebra,TIWdrsign was based on that of Kirn’a chambers uecd by theZPR-IR group at ANL, Idaho, and incorporslcd a number of im-provements. in particular, ihc’wall thickncas waa reduced toreduce the degradation of the spectrum. The fissile coatinga inthe earlier chambcra were prcpamd by a painting techniquennd those in the later chambers by an eiectrodepesitton mc(hod,TIWmass deposited was dctcrmincd by low geomeiry a-assay.The construction of the chambcra mwf the method of calibrationand use are described. Centrai fiaeion ratios in six Zebra coresmeaaurod to an accuracy of 1 to 3% are compared with valuescomputed uafng the FD2 daia eet and the CRAM or SCRAMBLEmultigroup diffusion theory programa. ‘l%ia comparison aug-gmts that the calculations give too few ,neutrons at high energies.There is IIiso evidence that somo of the ftsaion cross-eectiondata used in ihe FD2 set Ie in error. (auth)

‘s3454’ (BNWIAt28) PLUTONIti UTTLIZATJON S?RO-GRAM. Tecbnfcal Activities Quarterly Qeport, March-May 1966.(Battelle~Northwa@, Richland, Wash. Pacific Northwest Lab.).

. Sept. ,1968’. 67p. Dep. CFSTIJ ., CRITICALITY ST WDIES— meaaurementa ci critfcal number of

alumbntm~plutcmium fuel reds In water moderator, effect dI ~lattice pitch and boron concentration cm; micreacopic lattice

‘ parameter measurements on water-motieratcd plutarium ox-ido ( PuC$) -uranium exfdo (U~) rede: meaauremcnta d borcawortli end ooncentraUm for cold apd xences-free PRTR BatchCore

NfXJTRONS-capfure-te-fiselnn ratto meaauremcnts in piu-toriium-239; multiplicaiton factnr rfrtcrmirmtien fn waicr-modemtcd plutonium nxkfo ( Pu(ls) -uranium oxide IU%)lattices; rcarmance escape prohabllity detcrminatiois forumnlum-238

.,38305 SIMULTANEQUS MEASIIR1. MENTS OF Tlifi ‘s>(lFISSION ANi3 CA PTUitE CROSS SEX’rKJh.>. Wetif.m, L. W.(oak Ridgo National f.ub., Ttmn.); CvAu, 11.: du *IIs~ure, G.;Ingla, R. w.; Fuilwood, R. R.; Hnckenbury, R. W. Trans. Amer.NUCL Sco., 10: 220-l (June 1967).

From 13th Annual Meeting of the American Nuclear -iety,San Diego, Calif., June 11-15, 1967. Set? CONF-670602.

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66



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18298-.-—. -.

MEASUREMENT OFTHENEUTtiN CAPTURE A24DFISSION CROSS SECTIONS ANDOFTHEIR RATIOALPHAFORZtafl, Zsiuo AND 2$9Pu. de Smmeure, G. (OakRidgeNatlonafLd3.,TrM.): Wcrrtcm,L.W.; Gwin,fi.; lngle,R.W.: Tcdd,J.If.;Hockentmry, R. W.; Fulltvood, R. R.: Lottln, A. PP 233-49 ofNuclear Data for, Reactora. Vienna, International Atomic En- ,ergy Agency, 1967.

From IAEA Conference on Nuclear Data, Paris. See Sfi/P\l R-140 (Vol,2); CONF-661014-fVol.2). ‘

A tcchnlque was developed to measure a{multaneously the neu-tron capture and flapion cross scctlonn of flsslle nuclel. Sincethe two cron8 ricctlon8 arc mca8urr?d nlmultaneou.!rly, errors aa-aoclatcd with unccrtain(lea in the relatlve energy resolution andcalibrntlon of the two meaauremente are ellmlnstcd. Measure-ments of u= and crf for 22SUIn the neutron energy range of 3.25 to25 eV hnve been published. These measurement have now beenextcnrlcd to cover’ the range of 1 to 100 eV, and the precision andenergy resolution hnvc been greatly irnprovcd. The fl.v.vlon crossacctlon In In grind ngrcemcnt with recent measurements usingd! fforcnt tcchnlqucrr. At low energy, where the hratrumental re.a-olutiorr in small compared to the Dappler broadeolng and wherercwmrancc scattering ia unimportant, the directly measured cap-ture croee aectlon 1s consistent over many of the resonances with .that obtained indirectly by subtracting the fisalon and potentialacatterirrg from the total crorra~section. The capture and fisaiaoresonance integraiB and their ratio aR1. obtained from our mea-surements, agree within the uncertalrrtiea’with the direct integralmeasurements @fthese parameters. Further measurements on2~5u a“d 23W over the n’eutron energy range of 1 eV to a few keVare now in progress. The Iimitatione of the experimental methodare diecuaaed, and a detajled coplparison of cross section.x ob-tained by differekt,tectmiques are preeented. To compute thebreeding ratio, the Doppler coefficient, and other parameters oflarge faat power reactora, it is important to know a, the ratio ofcapture-to-f imrioo, for the main fiaaile iaC40pea, and particularlyfor ‘SDPO,in the keV neutron energy regiori. Hopkins and Dfvenhave performed direct measurement of a for 13~, ~~U, and ‘s%with monoenergetlc neutrons at 30, 60, and above 175 kev. ~tha value of n for ~~PU variea by more than s f~clor of two hetmQ?() :!IZ,IGOk,, \,. and n dt~tnilr.ri l,m>wlwl~v rif the varintion of thisp,rln,,.trr with rncr~v in the kcV nrutrrm cncr~y rnngr nppwzrsrtreiz’altl{$ “rhc npplirn! Ion of the t{mc-of - fll~ht tcchnlquc prrrmltrzr-xlcnrli~ the tilruct mc.nsurt~m(wrln of rr to cncr~trrr where mono-rncrcvt {c ncut z’rrrr.w, urccs a r{, not rcnrfiiy av~llnhlc, Dclnllcd mca-rwrcmt. nls for n for ?lJPu nrc now in prngrr as, nt fvw-kcV inter -vnle in IIIC ran,qc of 1010 100 kcV nmi at 100-krV intcrvnln in ther~nu,$ ,If 1WItu 600 kcV. The lechzrlquc hn# aircody hccn used withXII ~“(1 the , ~.UIIS$ now pul,iishcd. were found In El?rccmcnt wlihthrew of IIop!iim nnrf ~ivcn in the raogc of overlap. The results forz’~pu nrv con!pnrcti with timsc of Hnpklna and Divcn and with valuesof o t.lda Inm! (mm direct mrnsurvmcnti of v hy Spivnk et nL Thefnrtnrx Ilmltllw thr prcclslrrn of the mrmfmremcnts are di8cua8edIn stt,nc ,irtntl. (:LuI{I)

35288 (BNWL-774) PCTR INTEGRAL MEASUREMENTS OF?>SI>UALpHA ~ IN FAST SPECTRA. Lanning, D. D.; BUSSel-man, G, J.; Bennett, C. L.; Newman, D. F.; Biermrm, S. R.(Batteiie-Northwe8t, Richland, Wash. Pacific Northwcet Lab.).Apr. 15, 1968. Contract AT(45-1)-1830. 42P. Wp. CFSTI.

An analvsie of {he fcaatbility of integral measurement of ~ for .Zwp” in the phy8i~al COn~~ntS Test Reactor (PCTR) as a fUnCtiOn

of the carbon-to-uranium ratio in plutonium oxtdc-uranium oxide-carbon mixtures {e eummarlzed. The exparimente proposed willuse 9 to 14’7 PuOZ (of low Ztopu) in Uo2 mixed with graphite. It is

concluded that integral value.v of iZ ftrr 23SPUcan be mcaaured inthe PCTR with an uncertainty leae than +0.06. (D. C. W.). . .

18291 MEASU-REhENTS OF ETA, ALPHA, AND NEU-TRON CROSS SECTN)NS FOR a8Pu ON THE HARWELL NEU-TRON TIME-OF-FLIGHT SPECTROMETER. Patrick, B. H.:Schomberg, M. G.; Sowerby, M. G.; Jolly, J. E. (Atomic En-ergy Research Eetebitahrnent, Hanvell, Eng.). pp 117-27 ofNuclear Data for Reactora. Vienna, Intematlonai Atomic En-ergy Agency, 1967,

From IAEA Conference on Nuclear Data, Paris. See STI/PUf3-140(Vol.2); CON F-661 O14-(VO1.2) .

Eta valuee and total and firmirm cross qectione were meaeured 9j u81ng the Harw,eli 45-MeV eiectron linear accelerator neutron

time-of-fright spectrometer. The 34.9-m flight path, wltb a reso-lution of 7.2 ne/m, wae used for the cndrgy range 10 eY to 1 keV;and the 97.5-m fright path, tith a resolution of 2.5 ns/m, was usedfor the energy range from 50 eV to 30 keV. The experimentalmethode employed were similar to those of Brooks et al., in whichthe fission neutron yicid and the tranami.veion of a number of sam-ples of different thicknesses are measured together with the shapaof the incident neutron spectrum, all tbe meaaurementa being madewith the mlpzc reaolutl on. In the ylrid mranurrmr.nta, fnst m.utronefrom fission cvrntn were rlctecterf in liquid Rclntlllntore, and pulae-eh:lpr rllncrimlmt inn vme um=d to r<.jf,ci evcnte caum-d bv Rnnlmaray~. The trzinnmiz?dmr mci{surcmtnls were pcrforrnm-1 with ailthlum gla~~ nc!rrtiliator, and a l/V detector was used to mea-sure the npcct rum. l’!uckgruundR were mcnnurcd unirrg tbc “Chlackrcnmrnncm=” technique. The mraauremcnt8 at 34.9 m were nor-malized In the region of {0 eV to the eta vniws ohtaincd by Broekset al. and the cin vniuce from the 97.5-t_e measurements werenormniized to the 34.9-m memmremente in the region of 50 eV.The reoults were correoted for multiple ncatlerirrg in Jhe nampiea.,., ..- —.. .— -..

Cnpture cross SeCtiOnS wCrC’dtvivcd from the total and fiss{oncromr nccti OnRby atmumlng vnlurs for the scattering cro~~ acc -tlon. A dirrct mcnnurcment of nlphn (the rntlo of the ~nptllro to.fhnion crow twctlmwd 1s in progrees over the rnergy runt:,, iOrV 10 30 krV. Thi8 will icnd to a better estimate of the c.!l,t,ire~rnnn ecctlona ~ince alphn nlcaeutcmcnte are not no e(.neitive tothemagnlturfe of the scattering crose section. (auth)

37364 MEASUREMENTS OF 2a6UAND 2S9PUNEUTRONCAPTURE-TO-FISS1ON RATIO FOR RESONANCE INCIDENTNEUTRON ENERGlkS. Ryabov, Yu. V.; Don-Selk, So; Chikov,,N.; yMWao N. At. Energ. (USSR), 24: 351-62 (Apr. 1968). OnRussian).

The bcutron fission cross ecctions and capture-to-fission ratiosof 239Pu end 3SSUwere meaeured in the neutron energy rangee S eVto 23 keV and 0.15 eV to 30 keV, rcspcctivrl.v, using the timc-of-fiight method. Fistrion evente were rcgistcrcd by delayed coinci-dence between prompt y-ray puiacs and slowed fission nrutrone.The counting rate of capture events waa determlnwi by the antico-incirfcncea. Tbe capture- to- f!aeion ratioa nnd the fission crosssections are presented as functions of energy. Values of the cap-

:ure and fission resonance integrala are iabulatcd. (D. C. W.)

67

1968

3s345 NEW METHOD OF MEASURINO AiPHA(E) FOR 21SPU.Schomberg, M. G.; Sowortry, M. Q.; Evans, F. W. (Aiomio EnergyRese*rch E@tabl[shmcnt, HarweH, Eng.). pp 289-301 of FastReacWr physics. Vol. 1. Vienna. International Atomlo EneruyAgerwy, 1968. -

From Symposium on Fast Reactor Physics and Related SafetyProblems, Karlsruhe, Germany. See STI/PUB-165(Vol.l);CONF-6~1043-(VOl.1).

A special llquld aclnttllntor detector has been developed for thepurpose of mcaaur!ng alpha(l+) for 2S0Pu ha tho energy range 10 aVto 30 kcV tmlng the liar-well Llmmr Accelerator time-of-fllghtspectrometer. Alpha(E) fs the ratio of capture to fitslon orom

mvllona na n function ~f incident neutron energy. The detectorhnn two outputn, mm responding to gnmrna- ruy Intcractlons andthr olhcr to fnrit neutrons. The efflclrncy of. the rfotccior for~nmmn rays 16 rtrrangcd to be proportional to the gamma-raycncrKy. Thiti prormrly Is nchlcvcd by utlllzing nn ImprovedMoxon-lino dcslgn and cneurce thnt the cfflt’lcncy of the detectorfor rnctlntlvc capturo events is conetnnt irrcepoctive of the natureof the gnmmn-ray cnacncfc. Tho fast neutrons nrc nlflo detectedin the liquid aclntlllator and pulse shape dlscrlmlnntion la ueedto reject events prcduccd by gamma rays. An n gnmma-ray de-.tcctor the device 1s scnsltive to both radlativc capture eventsand to the prompt gamma rays preduced in fiaeion. However, acorrection for thin latter component ie made using the Informa-tion from the fast neutron output which is essentially only eenai-tlve to fiselon cvmrta. For each of the time-of-flight timingchannels the ratio of the corrected counts from the gamma de-tector to the number of ftasion events detected is equal to K xalptrs(ft), where K 10 a conetant determined by normalization.The technique of measuring both capture and fission simultane-ously ensures that hroident neutron enc~y apectmm chargee andresolution effects are unimportant and also reduces the multiplescattering corrections. The detector rryatem ia described andsomo of the data ob~ained are shown. (auttr)



6601 INSTFIIIMENTATION TOMFA90RE THE RATIO”6FNlil’”rR!lN C’APTURE Tf)FISSION,CROSS SECTIONSATkeVtiEVTH(tN ENERGIES. Torfd, J. H.; Weet.on, L. W:: Ingle, R. W.‘(Ouk Nidge Nutionaf Lab., Ttmn.). Coutrtict W-7 W5-ei~-26.Nucl. hmtrum. Mothod~, 58: 143-50 (JJn. lYfIb). Njl{NL-l~39S6).

fmnrumcntuttcmfor moeaurcmcut of u [thu gtmuuf thet,eutron“ca!iuro uruaa twctlon to thu ftanluu crutin oecumd wtw dcnlgmd,

WPCIIIIJIKA,und culllmtitcti, Mud mc.nittrenwutu n{.rc nude fur2J811U233U ~d i~5fJ at ncu[run uiwrglcs frum 10 tII IJW ku\’. ‘f’hr!,,

,detecior conslsied ofeight photomultipiier tuba located aroundtbeperlphery ofa210-gal tank ofgadolinlum-loadecfl, uidticlntll-

-$later, Thetlme rcsohatloo of thesystemwaa6.5~10 secuntteroperatin condiUonrr. The energy reaoiution at the 2.5-hfeV sum

Fpeattof 4Cowaa 35%. Mmtronenergtes wero measured bytlme-of-fright techniquee trelngaflightpmh of 1 meter. Fisslun eventsw&e dlettn@ehcd from ciiptu;e evcnta by the dctcctlon uf thcr -miiilzcd flselon ncutrorw foilowlng iho primary events. hfcimurc -ment of the rotiitlve efflciencyof the lurge scintillator Cmk furdetecting capture and flssionetentswas mwiebyslmuit.mcuutilycompiling ihe background md forc~~ound pulso-hclght spectra forbotithe captufe and fitielonovents. Typlciai fqwctruforthencu-truntime of flight forcapturoamf firtaloncvcmis ahmgwiththtibuck bwound and forogrcnmdtqwctru or both tMwti uf rwnts aru~hown. ‘1’lwt.twhnlqucs und ad]uutnwntu ueod tooht, thi thu ilmblgroaoluthm.tm thu hirh~’ b~nk Urw discutwxl.’’l%c Iuglc.ncxwm.frryfordimlillbwiShillg fitiB[on cvtmt~ andtho fOrt’hTtJUIldami buck~rmuxfpuitw-height rninwtra nswwluicd with bvth typcti uf uwm ur~! do-scribed. (uuth) . .

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.

32589 AN INVESTIGATION OF 2S1PUALPHA IN THf? keVENERGY’RANGE THROUGH SOME LATTICE EXPERIMENTS.Eehgal, Bal Raj; Price, Glerm A.; Windsor, Henry H. (BroOk-heven Natfonai Lab., Upton, N. Y.). Trans. Amer. Nucl, Soc.,11: 202-3 (June 1968).

From 14th Annual hfeeting of the Americatr Nrtolear WcletyoTorontf. S.ee CONF-680601.

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68

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5. Resonances

1967

4318 NEUTfU)N-SPECTROSCOPIC INVESTIGATION OFSEPARATED SILVER ISOTOPES. Muradyan, G. V.: Adamch&

Yu. v. (Ktmchrztov inst. of Atomic Energy, Moscow). Vlcnna, “Intcrn:ttl[m:il Atomic V.ncrgy Agency, 1!166, l]rq)rlnt No. CN -23/107, 24P. (In Russian). (C0f4F-661 tJ14 -27). lYrl I.:.

1,’rmn IAliA Confcrenceon Nuclear fhta, Pxrls.TIw rusults nrc prcsentcdnf mcarwrcm(nts ,m t)ie radkrtive

capture nf neutrons in the scpar:~tcd sllvcr lsob)prs 107AKand 10*Aginanencrgy r:m~e upto 1000eV, Anumlwrof previously unre-portcri Iovels were found. [1 [s shown thot the marked ,I[scrcpancyhctwccn the level-spacing distribution previously rcportr!d for AKand the Wigncr distribution for various superposed lCVCI systcma1s only nppnrcnt. It la also shown that there Is nocorrc!lation bc-twcwn lol~ and ~“~AglCVCIS within the limits of statistical nccuracyobtained. “Uhevalues of the strength functions SOfor ‘07AZ and !~g~are Cnund to be 0.43x 10-( and O.83x 10-4, rcspcc(ively. Thismarked diffcrcrmc In the fltrength function values of nuclei of al-most the same atomic weight 18 not conelstent with the opticalmodel of the nucleus and can probably he explained on the hypothe-SiS of compound-nucleus formation through three-quasi-particleinteractions. (auth)

17351 (KFK-452) HIGH RESOLUTION CI?OW-SECTIONhll’\SI’1~l’hlItNTF ORSl)hlE FAST REACTOI{ STI{UCTURALM.i’11 Rl,\L.slNTHftkcV f?NERGYllANGE. Rohr, G.; Fried-Iaml. E..: Nohc, J. (Kernforschungszentrum, Knrlsruhe (WestGermanv). lnstitut fuer Angewandtc Kernphysik). Oct. 1966.14P. (C.ONF-661O14-47). DeP. mn.

From I,\EA Conference on Nuclear Data, Paris, France.Trnn:mission measurements of the neutron total cross eectiona

~f Fe 51Fe st~[n, ancjsivat 20 to25o keV were made u91ng the

time-’rf-fli~ht method. A multilevel analysis of thedatafor S6Mnand$iv ,ie]ded reeonance pa~~meter~forthese ieotapee,anrf?lrl

arcm analysis of the data on Fe yielded resonance parameters for‘Fe. (D. C. W.)

11950 Mf)NTf? CAR LO CA LCIJLATIONSO FRESONANCEINTfiGRA L CJF 2nTh. %:h~l, Iial Raj (Brookheven Nationall~b.. Upton, N. Y.). f4ucl. Sci, fhg., 27: 95-103 (Jan. 19G7).@N L-l(J210).

I{ewmar,ce lnt(~riil c:tlcul:, tlwzti :irc done fur 2S2Th infinitedi)ute, ‘Sz’rh mela] rod, and 232T}102 rod sytilcms. I)ojqdcr effectcalculatlzms srw Iwrforuwd for ‘~z’rhf-+ rod rnygtcms for tcmlw, ra -Iures UI, LO2fJllJ””K. Thu rtisolvctJ rrsonance inl(.gral [or rod sys -tcmb at each tcmf,emture 18 uvtiluattid hy hiontu Carlo cslrul:mkmu

. . . .and the resonance overlap effect dtween the two resonanccrn of That 21.78 and 23.4S eV is taken-into account. The unresolved s-and p-wave contributions were ~ompted by standard methods.‘rho data describing the resolved rcfionance psramete ra up to3 kcV (I”y = 25.9 McV) rccommcncted in BNL-325 (SupplementNo. 2, 1965) are ueed In these calculation~. The p-wave strengthfunction in the unreaolvcd energy range is taken to be 1.b3 ~ 10+(eV)-~. The calculated resonance lzrtcgrala and Doppler cocffi -clcnts are compared with measurements; they are found to be inexcellent agreement with each other. (auth)

50617 AVEI?AGED RESONANCE NEUTRON CAPTURF IN(x’, u. AUcn, B. J.; 15trd, J. R. (Australian Atomic Ew,zgyCommission, Lucas Heights). Phys. Lett.,2~B: 494-6 (Sept. ~%19(IQJ,

The In[ensi.i,.- of resonance averaged yrays from th~ captureof IO- to 60-krV nclttrons in gold were meatm red with a t;e(l,lldrteclw. Transition .stren@hs to final states between O.2md 1.2hlcV have strorg El reduced widths andprovideevidencc foradcnifimn( 4s-:IP direct component tn the capture mechan[sm.(a~thl

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69

1968

35346 ~ NEUTHON CAPTURE AND FISSION CROSS-SECTIONDATA IN THE keV ENERGY RANGE. SOME NEW MEASUItE-MENTS AND RENORMALIZATIONS. Bcckurta, K. H.; Kompe,D.; Menfove, H. O.: PoentIz, W. P. (Kernfomchurrgszentrum,Kcirltrruhe, Ger.). PP 67-76 of Fast Reactor phY81cs. VO1. I.Vienna, Internetlonat Atomto Energy Agency, 1968.

From Sym@sium on Fast Ree,ctor Physics and Related SafetyProblems, Karlsrube, Oekmtmy. Bee STI/pW3-165(VOl.l);CONF-6’t1043-(Vol.1).

Somd new mensurcments of capture cross nectiona were per-formed using the 3- MeV Karleruhe pulsed Van de Graaff accelem-tor. A major effort waa undertaken to measure the absolute goldcapture cross nection an a function of energy between 25 and S00keV in order to eetabliah a reliable etandard for capture andfission cross-section renormalization, TO do thts, a well-collimated pulsed beam of monoenergettc neutrons produced ina thin lithium target at 80” to the proton beam direction wan usedto Irradiate a O.I-cm thick aarnple in the center of a large liqutdscintillator which detects the prompt capture 7 mtys. The rela-tivo neutron flux was meaaur@t wtth a‘ ‘grey neutron detected’which 1s relatively Inacne!tive to neutron e~ergy vertationa. in tbeenergy range of these meaauremente. The gold croae~sectlonahnpc wee normalized at 30 keV to an absolute value fitted from

croee aectionof%lvarious recent e erimente. By a similar technique, the capture

U in the energy range 25 to 500 keV wan deteemtned, Furthermore, cross .eectiona of several medium- andheavy-weight nuclei which may be of some ipterest to reactor de-sign (Nb, Mo, Cn, Hf, Ta, W, Re) wet-q determined by a time-of-fllght method, ueibg the gold value ae a etandard. The, data arepresented, and come implication of the new data on reactbr cal-culation are reviewed. (auttd

48522 [LN4917) A ML!LTILEVEL ANALYSfS OF THE 23SUF[ssN IN CRCiS. SECTION. Cramer, James D. (Les AlamosSrletrtific Lnb., N. Mex.). Apr. 16.1968. Contract W-7405-eWT-36. 9P. Dep. C FSTI.

lk?sonwrce parameter [or the ‘tU fission cr’cum section,, asmeasured on the Petrel experiment at the Nevada Tcet 51te; wcrddetermined ushrg a multilevel fitting program baecd on the Wigner-Elsenimf R- Matrfx theory. (auth) .

.-53168 (JAER1-1162) ON THE hWALU~TION OF 219Pu DATAIN THE keV AND RfMCILVED RESONANCE f{ECION. fhrston,C. (Atomio Energy Eetabliahment, Wlnfrlth (Engl+)): Kat-auragi, S. (Jnpun Atnmlc Energy Roscarch Inst., Toknl. TukaiResearch Eetablishmont). JUM 1968. 10fi. Dep.

Thu evaluation for ‘S$pu cross scctium In the keV rcgiun isdeacrlbed. The piwaent waluntion gives a bettur inlcrprctuiiunfu buth the a value and the Citmlon cross sectlun. T}ds evalutttitinconfirms the applicability of the chtmnel theory of fissiun. Inthe reaolvcd rosormnce regions ● fit to’ the CIXMSsection iti uh-.tained that in auitoble for use with. the GENt:X cwde. Fur uacrsconvenience, the reeonance parametcnw ure list~~. (suth}

Neutron Cross Sect ions:

5. Resonances

60834 F18310N COMPONENTS IN 284URESONANCES.James, ~. D.; Rne, E. R. (Atomic Energy Research, Eatablteh-ment, HarweI1, Eng,]. NucI. Phys., A118: 313-20(1968).

The fisaton cmse section of 2S{Uwas meamrred in thn energyrange below 20 koV and shnws three regtons of etrong flsslonyield with essentially no flatrion at the intervening energioa. fnthe firet group, which covem the energy rengo up to 740 eV, all ‘

,the 20 resommcca known to extat below 370 eV in the totaf croeasection havo a measurable fission width with an average (rr) =0.098 MeV. The second and third gmupe are centered at 8.33 keVand 13.9 keV and extend over about 1 keV. The area under thefiesion cross section curve c,l”f 1s 97.7b o eV for the 29 reso-nance below 74o eV, 92 b . eV for the group at 8,33 keV and32 b . eV for the group at 13.9 keV. An analysis of the di.etrfhu-tion of fission tvidtha for tbe 20 reeonancee below 370 ev ahowcthat they fit a X2distribution with v = 1.39 ● 0.37 degrees of free-dom. Thin evidence for a grouping of rmb-threshold fisaton reeo-nancea is similar to that already found in 2oPu end 2s7Np and ac-cording to Weigmam and Lynn is a result of the exietence of theaccond minimum in the flae.fon @eotiaI barrierm m~ic~edbyEtrutineky. The well depth corresponding to a level density of7 keV indicatee that the 4ccoid minimum Mea at 3 MeV above theground state of ?XU. (auth) :. .-.,. .

39637 (RPI-328-123, PP 1-17) NEUTRON CROS9 SECTIONS.tReneselaer Polytechnlo Inet.,TruY, N. Y.).

The average capture croes aectionn C4W, ‘2W, ‘SW, ‘iW, and*OWIn the ~nergy ra~e from 1 to 100 keV were doterminecf. The

I

p-wave strcn@h functions for ‘Fe and sNi were extractrd fromcnpturc datn, nml the radlatlvc width 0[ the f. G-keV rl,pwmncr InWNI ~ae d,.tpr,nlned. The tOtai croes aectifrn ~ 141Pm W’andc -

termlncd by trnnnmlae[on measurements on f~flr 147pml% sam -ploe over the energy rnngc from 0.008 to 200 eV; nrutrnn rmm-nnncc pnramrtern were obtr.incd for cnerglt?e UP to 12n I-V(f’).c.w.)

3723 NIz1’TRON RAfXATIVE CAPTURE IN Mo. Wclff- “~Mn. II : Schmld, H. (Euratom, Gecl, Belg.). Nuc1. [email protected] 513-24(1967).

Ncutmn radiative capture In natural Mo wae etudlcd In the ncu-trunenergy range from 10 eV to 25 keV. An area mmlysla was ap-plied to part of the observed resonances which yields gr. forsmall remmances or r, for large reeorrences. Above 1 keV neu-

tmrr ener8Y, the Obemwd capture rate was averaged to give themean capture croaa se~toa which {a tn good agreement withe&lt8r measurements. (auth)

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70

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6. Doppler Effects

1967

38318 Ll<YSrALLINk: k’t’FiiCTSON’i’I{E LIOPPLfiR-BRO.ADENEDCROSS SE~TIt3N ANDRESONANCh INTEGRALSOF URANIUhl INAU~ LATTICE. Adktns, C.R. (CarnegieInst. of Tech., Pittsburgh); Pcrslnnl, P. J.; IIwnng, R.N. Trano.Amer. Nucl. Soc.,10: 228-!) (June 196’7).

From 13th Annual Mcwtlng of the American Nuclonr Soclpty,San fXego, CnlIf., Juno ll-15,19G7. tio CONI~-C701302.

42611 (NAA-SR-12501) HIGH TEMfWRATUHE Ml?)\ SURE-htI:N~S OF Wl)l>LEREFFF.CTIN UC AND UOIBYMf!THODok” TFMPKfLATtlRE-CYCLKfl RftACTIV1”rY OSCILLATION.fkllrr, L. S.; Hencveld, W.H. (Atomlcs International. CmiogaPark, CnUf.). Aug. 1, 1967. Contract AT(04-3)-701. 33p.Dep. CFST1.

Interim mcasurcmcntsof the Doprdcreffcct lnnominally 0.5-cm-dlamctcr samples of natural uranium carbirlr and uraniumdioxide arc repnrtcd (ortcmperaturcs up to 1330”C. The mca-surcmcnls wrrc made as part of the Invest lgatirm of thv methodof making Dnpplcr-c+fcct mcasurrmmrts by oscillating the tem -pcrat”rc toproducc a direct mrasurcmetd of dI/dT. The meaysurr-rf ratio 0[ specific reactivity effects for UC/U02 between1030 and 1330”CWSS 1.23 t 0.15, Unsatisfactory agreement withcalculation. The Dnppler effects in U02 are in agreement withcxtrnpolatimrs from data of others obtained at lower tempcra-turrs. The methods nnd rqulpmcnt for making Doppler-effect mea-surcmmrts by this method arcrfescribed. R is concluded that themethod is cntirr’ly practical, producing results of precision com-parable to that obtained hystandardmcthods. Certain advantagesof this mr.thod w’ere ugcd to identify quantitatively sources of, inter-ference. notaccessihie toothcr methods. (auth). .

35551 (ANL-7320, frp 334-40) DEPENDENCE OF InkDOPPLER COEFFfCIkNT OF REACTIVITY FrJR }tEAVY ELE-MfiNTs ON CHEMICAL FORM, SURFACE-TO-MASS RATIO, ANDNfl[JTRON SPECTRUM. Carpenter, S. G.; Mountford, L: A.;Springer, T. H.: Tuttle, R. J. (AtomIce. Irrternatirmal, CmnogaPark, Cal If.). ●

A series of experiments has been carrlcrf out In a fsst-neutronapectrtim, chnr.actcrlzcff by a median fission energy of 62 krV, inorder to measure the Doppler cocfflclent and otier related temper-ature cfferts for a varlcty of materials which arc of particular In-terest in fnst nwcr rractar technology. SpcclaI empha~ls has beenplaced on the ~’5fJ Isotope which has hecn lnvcstlgatmf [n severalchemical forms nmcirab]e to utilization [n high-temperature, hlgh-efflclcncy fuel Uements. Ch,ehges in the size and chemical compsition of somplcw of this isotope and other heavy-clement isotopeshave been made in order to evaluate the effects on the Dnppler coef-ficient of chmges in the surface-to-mass ratio and changes Inducedby the addition of C or O t,o form carbides and oxldcs. fn addition,the cf[ects of localized spectrum perturbation on the Doppler coef-ficient of Th have been studied by surrounding the sample with“bhmkcts’’”conslstlng of heavy reeonmrce absorbers, structural.~a!cririls, andseveral types of scattcrere, fncludlng Na. (autb)

35679 (AN1.7320, iqj 345-9) ftESULTS UK f{iJCi?N’f’ f)OPP.LKI{ h:X\~Ei{iMi. N’rS [N Y.[~[{-30 GwsIdlo, J. M. (Argonne Na-tionai fAA,, ld~h(, Fulltil kttiho).

Thti rernults of f>jppl w uxperlmcnts in Z Pi?- 3 (idtiho) arc pre-Wnled Tl,e ti~l,,.~lm,,l,tti were dune on two corm: nnc witichUrr”ud UM~ S} IS(JH lll,,(.kup and the (jthtit which WIUJfor pnrfi(!i-pallur, III tho hjlt.rlj.ttl,,nul C!c,mi,ariuun. iiuucttvity IIMIaUL’CMCnt8duc iU cbunge in n,utcl:itil~ umf torr.pcraturo,aro prerncntcd; Dupp-lcr effuct ~eatmrement twnultu uro rnhown km both atitiembiieu.fM. L.S.)

38604 ANALYSIS OF SMALL-SAMPLE DoPPLEf@E~=cTMEASUREMENTS. MS, R. A.: Till, C. E. (Argonne Na-tlowd Mb., D.I.). Trana. Amer. NUCL SOC., 10: 274 (June 1967).

From 13tir Annual Meeting of the American Nuclear SOc4eW,.%n Dtego, Calif., June 11-15, 1967. see CONF-1370602.

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6. Doppler Effects

3868S VERfFICATIONOF DOPPLER MEASUREMENTS fNZONED FAST Critical ASSEM’BLfES.’ Lewts, R. A.; Tiil,E. F.; Groh, E. G.; Le=ge, L.; Marehali, J. E. (ArgonneNaticmaI hb., DI.). Trans. Amer. Nucl. S@., 10: 273-4 (Jrme1967).

From 13US Annual Meefing of the American Nuclear Society,& Diego, Cal\f., June 11-15,1967. See CONE-670602.

35552 ‘(ANL-7320, pp 341-4) DOPPLEfi COEFFICIENTMEASUREMENTS IN THE CRYOGENIC TEMPERATURE REGION,Moutford, L. A. (Atomlcs fntemational, Canoga Park, CalIf.)..

The Dappler-coefficient haa been ~eatmred in the cryogenictemperature rmge. The fnveree ~emperature dependence of Usecoefficient rcaulta In relatively larger rehctlvlty changee at lowtemperature, aIthough crystalline binding effecte begin to be slg-nif icant fn this range. The ef fectivo-t emperature medel has beenuecd to correct for binding effects. The power fluctuations, as anample wae oscillated In and out of the reactor, were Fourler-nnalyzed to give the mactlvlty effect of the sample. Differentsample temperatures were obtained using a “Cryo-Tip” refrig-erator, which uses JouIo-Thomson expansion of N and H to cooltho sampkt. Measurements are reportqi for Tb and W in a 62-keVmedlon-flasion-energy spectrum. Also fncluded are mesaurementaat higher temperature to cwer the temperature range from 100 tolfJOO’K. The meaaured temperature dependence of the Dcf@er ef-fects agree well with calculated values, with Use cryatalltoe btnd-tng effects being evident trr W. (au%)—

10014 MEASUREhtENTS AND CALCUL.4TIONS OF THEDOPPLER EFFECT ON Tl[l; HEACTIONS ~]tlf(n,yl, 2wU[n,f), AND?l@u[n,f) WITH NEUTRONS IN THE ENERGY RANGE II Tl) 25~eV. Perkio, J. L.; Flcldhouse, P.; Bs’ick~tock, A ; IMvIc-s, A. R.fAtonlic Weapons Research EstaMishnwnt, Aldermaston, Hng.).J.Nuc I. Energy: l)t. A and f3, 20: 9,21-J7(Nov –IJc~, l!Jwi I.

SpkerIcnl samples, 2 cm in dipmct’. r, ,)f Z~~U,2~~u ~nd :,~IM ~t.reirradiated in turn at various teanpc,rrturcs ranging from 170 to‘771J”KIn u central cavity of a sph(.ricmlly symmc.tricui S1>- tit, Ijho-tmcutrrm source. The ?]OU(n,y) ~t,tictlcm rat~. WVMnl(,tisur,.d bycounting ttw 2$aU activity produccei and tile (n, f] rcact!wis weremontumwd by counting the fission nt,utrnns c.mtttuwf. lltt, sIdi, $rIcaleymmctry of tiw apparatus wus clwst,n to mmlmize uny t ilccts 01fhf,rnltd t!xpan~ion and (0 t~ciliiatt. thL. LWll]llLI~iSOnd !h(. lk’SUltSMuincxf witii ihwtt. from a comput~. r culmslul ion basvd ‘m u ,w,]-guummc d(wcitqwd by Brisscnden ml fhrston. In tkis progl ;tmII ~tuiistical distrihutlon of rusonunct.s bfisvd un ~i.s”j, ,.11r,.s,,-nancc data is tu~ulutyd over u fine c,n{.rgy mt.~h. Thi? tfil,ulat,onwa8 USL”dh a q-rL@OO ShJWing dOWn Cai CUiKtiLIn IItSUi[lllg U1Nruglcm-dcpcmdynt nc,utron spectrum f mm which UW imrtlctii:tr rt. -actkm rutc.a at varfmui Ii.mlwrafuros were obluinl,d. (quUU

.

‘ 38373 “MEAsuREMEi4T OF TfiS DOPPLER EFFECT FOR “23SUcApTuRE Am ~~suFf~fON IN A FAST NEUTRON SpEC-

TRUk& Plasterer, George Russell Jr. Stanford, CaJlf., .

Stanford Unlv:, 1966. ‘ 190p.Theslet.

.

‘ ‘fire Doppler effect in 238Ucapture end 23SUfission was measuredby means of a foil activation technique in the fast neutron spectrum .

core of the Mixed Spectrum C rttical Assembly. Experimental re -mdts were obtained for two 2StU foil thicknesses and one ‘JSU foilthickness. The amount of tr~attering material between tbe hiland surrounding core fuel wae varied to determine the effect onthe Doppler measurement of chknge in the incident flux fine energystructure in the reaonancee. In this experiment only the foil isheated, while the core fuel remains at room temperature. Themeaaufed 2s0U Doppler effect expressed as the ratio (change in

; foil activity with tempera’ture/reotrr temperature foil activity),R-1 was a factor of h higher than that calculated using a neutronenergy spectrum derived from ctnominal’~ materiai cross sec-tions. Presently available croaa soctiona its the energy range ofinterest are sufficiently uncertain so that ii is possible to inferfmm them “haSYI’$ or “soft” neutron energy spectra such thattho value of R-l varies by a factor of two. The meaaured valuesfor 23SUagreed quantitaiiveiy with those found from the “soft”neutron energy spectrum. Within the precision of the meamrre-mcnt no ‘3SU Doppler effect wae observed. The calculated 3aiUDoppler effect was smaller than tbe geneitivity of tbe experimentthus Within its precision (+0.002) the measurement confirms the

i theory. (Dieser. Ahstr.). .-

..-./ 35695 (ANL-7320, pp 569-S4) APPLICATION OF THE

SEEOR CRITICAL EXPERIMENTS AT 2PR-3 TO SEFOR.‘ Reynolds, A. B.; Stewart, S. L. (General Electric Co., SanI Jose. c~lif. Advanced Products OneratiOnL

I A ;eriea Of critical experiments. Wae pe~formcd with a mockupof SEFOR at ZPR-3. And yaes of thcae &pcrimcnta and the appli-cation of tie resuits io the SE FoR design are discussed. Valuesof the criticai mass were determined for 1-, 2-, and 3-segmentSEFOR fue] cfcsigms in order to heip establish the PU atom frac-tion In fhti SEFO]i futi]. Reactivity effeciti of axiai fue] Cxpanaionwere meutiurc~ which Icd to Bcicwtion of fhc 2-ticgmcmt dwsign forSEFOR. Meuurtimente of tko rcnctivlty worth uf thu rnsfitd rO-ftwtur cstaljlibhcd ttw adc.quncy of UW.SEFO!I rtificxlur-rxmtrolI stem. Tho Oupplcr cocfficic.nt was mcunured. Tho cnlcul:dcdILU ~ppler Cotiffic{cnt waa in agrccmcnt with h ~xpcrlmCntalVlhe; tbe measured 2~$pu contribution to the s}. f’tJit hppicr coef-ficient wm near zero. The maximum ~sltive rcac’tiyity due toi081JOf a“d{u~ Waa measured.. The ratio Of prompt-neut run i ifl!-time to de]aycd-nmtron fraction wa~ mcaeured both by Ike PUlaotfaeairun t~chfllque~n~by noitic unulysie. The vuluca mcasur-cd t.Iythe two t~hnlque~ wtirc in (,grcemcnt. Fieelcm rutiuti, fiuti ion andbaron traverscti, and p]”tul,lum wori}i difitribuiiona were tnCwSrOdand cumpar~ ~{th cfilcu{at{unti, A tint of i? rcfcrcnccs lb in-Ciudcd. faUth).

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6. Doppler Effects

3s678 (AN L-7320, PP319~33) ZPR-6DOPPLERM EA9URE-MfiNTS AND COMPARfSONS WITH T5iEORY. Till, C. E.; fJCWiS8R. A. I Hwang, ft. N. (Argonne Natlonul hb., Ill.).

The mdasu rcmcnta repurtcd were doa lgncd to study various aa-pects of the Duppkr effect fn a spectrum reltwant to a fntit powerreactor. The muthod used, was based on mcnsuring the reactivitychanges result tog’from the in-pile heating of smull aamplca fn azero-~wer assembly. After proof-teats of various ktnds, themCIbUrCIIN?ntS concentrated on: thO 2S8UDO Ier effeCt aa a flUtC-tlon uf rnample pize and chemical form; the % Doppler effect,with particular attention paid to evaluation of the extraneous ef-fects of thermal expanalon; the Doppler effect of mfxtures oft~~u ~d 2J2ui the effect of sodium voiding on the Wppler effectof ;S:IJ nnd 2~~U. A consistent Intercomparltxm of tho most pcrtl-ncnt re~u!tti, and a comimritjon of the rcsult~ with u cunnlatentset uf ealculutionti uulng current theory tire prcmmtcd. A list of14 refcrcnccs IS Included. (M .1,. S.)

38730 DOPPLER COEFFICIENT TEMPERATURE D!i-PEN7)ENCE AND THE EFFECT OF SODIUM VOIDJNG. Tfll,C. E.; Lewts, R. A.; Rind, R. B. fArgonne National Lab., fll.).Trans. Amer. Nucl. Sot., 10: 335 (June 1967).

From 13th Annual Meeting of the American Nuclear Society,San Diego, CalIf., June 11-15, 1967. See CONF-670G02.

1968

7920 (AN~-Trank540) INVESTIGATION OF THE DOP-PLER EFFECT IN 2S:U IN A SHIELD MADE OF URANIUM OXIDEOF THE REACTOR BR-1. Ahagynn, L. P.; GolubevO V. 1.; Gol-ynev. N, D.: Zvonarev, A. V.; Kolcgnnov, Yu. F.; Nlkolnev, M. N,;Orlov, M. Yu. Tr~nnlntwt from n paper presented at the IAEASymposium on the Phvnlc, nnd Snfety Problems of Fast Reactors,Karleruhe, German Fedv-rnl Refmbllc, October 30-November 3,1967. 14P. (C”ONF-671OI3 13). Dep. CFST1. JCL $1.10 fs,$0.W Mr.

The Doppler effect In 23RU{e studied by measuring the tempera-ture Increments of the effcctlve rcaonance Integral of absorption oftfdn ~%-oxide sample placed [n a Iargc block of U02. The Dopplerlncremcnt of the rate of reaction wan mcnnured from arm to ZOOIYK.(fl.c.c )

35640 INX’ESTKIATION OF THE DOPPLER EFFECT IN ‘, :3’{! IN T1[K l~Xlf)ft NLANKET OF THE nR-1 HfiACTOR.

Al,:,gynn, L. 1’.; Golubcv, V. f.; Golyacv, N. D.; Zvonarcv, A. Vojk,,lct:nmw, Yu. F,: Nlkolnov, M. N.; Orlov, M. Yu. (Physical- .Ent. rgy Inst., Otmtnsk, USSR). pp 317-27 of Fn8t RenctorPhysics. Vol. 11. Vienna, Internntlonnl Atomic EnergyAgtIncy, 1968. (In Russian). (ANL-Tra2m-540).

From Sympalum on Fast Reactor Physics and Refatcd Safety,Problems, Knrlaruhc, Germany. See STf/PfJB-165(Vol.2);CON F-671 O4WVO1.2).

fWu~lcs have been carrlcd out on the Doppler Incrcnsc In cnpturerate In thin tmmples of urnnlum-238 Irradiated itt a Iargc black ofdepleted (102 at room tcmpernture. The core of the RR-1 reactorwnn used an ncutrnn source. The neutron epcctrum at the pointwhere the Doppler effect mcaaurrmcnm were car~~d “tit wascloee tn the asymptotic spectrum of thb medium bring stm-fled.Nfvmvurcmcnts t.akon on thts spectrum In the energy range h~lo,w10 krV upin~ a set of rcaonance rlrtcctors showed satisfactoryngreemrmt with calculntcd dafn obtain~ frnm IJIc gy~t~m of con-afnnfe cvoltcd by \’. V. Bonrlarr.nko, M. N. Nlkolncv, L. P. Abng-yttn and N. (). Rn7nzynnts. The reaction rate In a hcafcrf samplevaa mcnsurd In rcIation. to that In a cold sample Irrmflatcrl at themtmc fms Itlnn 1? fAc rcnctor. flnmmh raya of energy 74 kc\’ ac-compnnlvwf hy hctn dr-cnv of 2J?U WC.rc rccor,lcrf. Men~ur~me”tnwrrc carrlml out [n thr tcmpernturr range 300 to 2000”K. Therffcct of the snmplc dlmrnalonn on the mcaaurcmcnt rcsulte wanestabllshrd, fle nlso was the effect of surrouncfln~ the eamplc by aInyer of acnttcrlng material (heater mnterta!, contntncr material,etc.). The accuracy of the results obtntncd WE 5 w 6%. It tsahown that In the temperature dependence of the proportlorml in-crease In the ‘~qU(n,y) reaction rate in a small heated sample canbe wrlttcn in the form: AA/A (Tz) = b(~– ~) where Tx =300”K and b = 0.0132 * 0.0004 (“fQ-~. The experimental value forthe Doppler increase In the z~%(n,y) reactton rate in a small snm-ple at Ta = 600”K agrees well with the calculated results, Theerror In calculating the Dnppler effect due to the inadequate knowl-edge of the neutron spectrum was not much grestcr than the errorin the exoerlmcntal data. (auth)

14027 THE DOPPLER EFFECT ON THE ~skf(n,y) REACTIONAT DIFFERENT NEUTR(2N ENERGIES AND AT HIGIf T&hi PERA-TURES. Flcldhouaei P.; PerkIn, J. L.; warner, G. p.; Brlckatock,A.; Davies, A. R. (Atomic Weapons Research Eatabliahment,Aidermnatbn, Eng.). J. Nuci. Energy. 21: 84’J-55(Nov. 1’367).

Memmrcmcnta of tho Doppler effect on the 23’’U(n,y)reactionwere made on uranium metal samplca, heated to 770’K, withneutrona of dtffcrent enorgioa in the rnnge O to 54 keV from thelLf(p,n) reaction. me meaaurementa made fn one particularenergy rahgo, (Oto 10 kev) were extecdcd to tempcraturea up to19f30°Kusing urmlum dioxide samples. The results obtalncd worecompared with computer calculations. fn the uranium metalenmplcs the fMppler effect at dlffcrcnt neutron energies wasfnund to ngrec, within the rather large experimental errore, wlfbthe theoretical calculations. In the uranium bxide samples themeasured Dnppler effect over the temperature range 290 to 1981YKagreed with that calculated, except for the first 200”K of thisrange where the mcaaured effect wa8 greatek than that calculated.(nuth) (UK)

33037 DOPPLER EFFECT TvlEASUREhlfiNTS AND ANALYSfSIN ZPR-3 ASSEMBLY-50. Gnsidlo, J. M.; NIchuleon, R. B. (Ar-gome National Lab., Idaho Falls, Idaho). Trahs. Amer. Nuc1.Sot., 11: 240-l (June 1968).

From 14th Annual Meeting of the American Nuclear Society,Toronto. 5ee cfJNF-G80Gol.

73

1968

33039 ‘SENSITIVITY OF SMALbSiMPI.E’UOPIILF:R EF-I,”K(:T MEASfJltI;aMflNTS TO liNVlftONhlLNT. LcWS, R, A.;Johnson, T. W. (Argonne Natlonnl Lab., 111.). Trans. Amer.Nuel. SOC., 11: 242-3 (June 1968).’

!’rom 14th Annual MccUng of the Amer]can ,Nuclear Society.Tqronto. See CONF-660G01. ,

32790 l{ECENT STUf.)lES OF TIIE DOPPLER EFFECT INHETElK3GE~i20US SYSTKk!S. Miller, L. fl.: Hu.ms, R. N.(Argonne National Lnb., Ill.). Trans. Amer. Nucl. Sm., 11:206(June 1968).

Frnm 14th Annunl Mectlng of the American Nur]r?r Society,Toronto. .Sec CONF-680601.

3706 ACTIVATION MEASUREMENT OF THE DOPPLEREFFECT FOR 2S8UCAPTURE AND 2StU FISSION fhf A FAST-NEUTRONSPECTRUM. Pffae.terer, C?, R. Jr. (General Elec-trlc Co., San Jose, Caltf.); .%er, R. Nucl. SCL Eng., 3& 374-94(1967).

Thc”llnppler effect in 238(Jcapture and ‘jStl fisdlon was measuredl,y mc.ms of n foil activation technique in the fast-neutron spectrumcore nf the Mixed Spectrum Critical Assembly. Expcri~ental re-sults w’cre obtained for two ‘~”f.lfoi,f thicknesses and one 2~SUfoilthlc$ncsscs. The amounl of scattering material hctween the foilan!] surrounding core fuel was varied to determine the effect on theO)pplor mcaauremcnt of change in the Incidrnt flux finr-energytarycturc in the rcmsumccs. In th,te cxpcrimcnt, only the foil ishe~tcd, while the core fuci rcmahrs at room temperature. The ex-prrlnwmt is mmlyzcd hy mcmm of the collkdon-protmhiiity methnduhich IS USCCItn ~icvclop and expression for the rcsomuice Integrainf a thin al]snrhcr which la separated frcm a homogcncoua reactor(u. I rq!inn by a fwrdy ncattcring medium. The general expressionfor the foil resonance lntcgrai 1s simplified, and numerical resulte .nrr prcscntcd for the case in which. thu dominant r$sonomce~ areweak; that ie, for n fast reactor in which the 0.5- to 3. O-keV energyrq!lon ddm Inatc-s the 2J8UDoppler effect. The measured ‘JEWDopp-Icr rffcct cxpreased as the ratio R -1 = (chsngc in foil activitywith tcmfwrature/room temperature foil activity) typicaIfy wad ofthe order of O.O15 + 0.002. Thie wan a [actor of 2 higher than thatcalcukitcd using a neutron energy spectrum derived front “nomiTnal” material cross sections. Presently available cross sectionsin the energy range of interest are sufficiently uncertain so that it “is pessihle to infer from them “hard” or “soft” neutron enqrgyspectra such that the value of R-1 varicb by a factor of 2. Themeasured values for 238Uagreed quantitat~vcly with those foundfrom the “soft” ncutrrm energy spectrum. Within the precision ofthe mcaaurcmcnt no 23SUDoppiei effect was observed. The caicu-Ialcd W Wppler effect wae smaller than the aenaitivity of the ex-pwiment, thus, within its precision (+0.002), the measurement con-firms the theory. (auth)-.. . . .


6. Doppler Effects

35626 ENERGY- AND TEMPERATURE-DEPENDENT CAP-TURE MEASUREMENTS 13E,~W 30 keV EUPPOftTINQ ~OPPLEREFFECT CALCULATIONS. Seufert, H.; Stegemann, D. (Kern-fo~schu~szentrum, Karkuhe, Ger.). pp 77-94 of Fact ReactorPhysics. Vol. I. Vienna, International Atomto Energy Agency,1968. (EURFNR~OO).

From Sympcsium on Fast Reactor Physics and Related S~etyProblems, Karlmuhe, Germany. *8 STI/P~-165(VoLl);CONF-671042-(V01 .1).

Energy- and temperature-dependent capture meaaurementa be-low 30-keV neutron epergy were performed th nafuml uranium,tungsten, and tantalum using the slowing-down time apcctrometertechnique. The experimental rtet-up used for the experimentsconsists of a led block of 1.3, m aide length conlalnIng two ex-perimental channels of 10 x 10 cm2 crone-section. Into the ftratchannel the target of a 14-MeV neutron generator in lntmduced,whereaa the second channel ie. used for insertfon of the heatedsamples. Pulses of 14- MeV neutrons, havtng a pulse width ofabout 1 Ma, are used. The neutron energy is degraded firat by In-

“ eIasUc coUisions; afterwards onIy elae~ic collisfona take place00 that d specific relationship holds between mean neutron energy

‘ in the lead plIe and the ttme after occurrence of the neutron pulsa. Because of thin time-energy relation a tfmd analyaia pmcedura

for the detector counts in applied. Because the energy range bs-low 30-keV neutron energy fs most interesting for Doppler-effectfnveatigattono the slowing-down time spectrometer 18 uacd tomerieu re the captu w ratioa of hot-to-cold samplea of naturaluranium, tungsten, and tantalum. Thin eamples were heated todffferent temperature for ~ja purpose, amf the capture y-rayawere detectr.d by proportional counters. Becauae hot-to-coldcapture rntios are measured a knowle@ge of the neutron flux isnot nmessary: therefore. s direct commtrison of calculated andmcaaured ternperahlre-dcpemfcnt cfosa-acctlona la poasibIe,A theoretical anaiyaln of the experimental fiats for urRhlum lagiven. (authl

32587 DOPPLER EFFECT IN % AT lNTERMEDIkTEs/fd VALUES. Sher, R.; Whttesel, R. N. (Stanford UniT..

\ CalIf.). Trans. Amer. Nucl. fkac., 11: 164-5(June 1968).. From 14th Asnunl Meeting of the Amerfcan Nuclear Society,

Toronto. See CON F-680601. ,. -.

5744 M}:ASL’REit ENTS OF THE TEM PERATURI? COEF-FiL’it:NT (W i{b.ACTfVITY OF 211U,~saiw, AND HiGilKR PuiSLlTOPi23. ~~u-inger, T. N.; ‘iWtIe, R. J.: Mwntfmd, L A.Lifomica Internsthnai, Canoga Park. Calif.). Trana. Amer.Nucl. SOs.O 10: 562-3(-NW. 19G7).

From 15th Conference on Remote ~stema Technology ●ndAtom Fair. Chtcago, Ill., Nov. 64, 1967. See CONF-6T11O2,

. .

33038 VARIATIONS lN THE FAST-SPECTRUM DOPPLERCOEFFICIENTS OF Th AND 211UAS A FUNCTION OF 2’ilE TYPEANI) TEMPERATURE OF TNE ENVIRONMENT. Sprin@r, T. U.;Tuttie, ft. J. (Afomic~ Intermt[onal, Cadoga Park, CalIf.). ,Trans. Amer. Nwl. Sot., 11; 241-2 (June 1968). .

.

.

74


6. Doppler Effects

32562 , (AE-314) ACTIVATION DGPPLER MEASUREMENTS0N2SaUAND 2s5U INSOME FAST REA~TORSPECTRA. Tlren,L. 1.; Gustafsson, I. (Aktlebolaget Atomenergt, Stockhohp ,’(Sweden)). Mar. ,1968. 40p. Dep.

Mcasurernents of the Doppler effect in ‘%f capture ‘md ‘SSUfls-slrm wtire made by activation t.fikhnique in three different neutrratspectra in the fast critical assembly FR-O. The experiments jn-’volved Irradiation of thin uronium metal foils or U~ disks, whichwere heated in a smai} oven placed in the cmre center. The mca-euremeats on 2~8Uwere exicndcd to l’f80”k and on ‘MU to 1470”K. .,A core region aurroundlng the ove~ was homogonizcd to facilltpkthe tnterprctaticm of rcsuit~. The. reaction ratca in the uraniumsnmidcs were ddccted by gnmma counting. The cxpcrimcntsfmethud was chcckwi with regiird to sye~ematic errors hy irrndl-aticars lo a thermal ~pcctrum. The data obtained for ‘% capturewere corrected for the cffcet uf neutron collisicms in the oven wail;and were extrapolated tn zero snrnpie thickness. fu thti suftbsttipt,ctrurn (cln-e 5) a Doijplur effect (reitk.ive Indrcaao In cupturcrate) of u 2611+ 0.018 wan obtatntxf on hunting from 343 to 171W&smi in t,hc.htic,icut npwtrum (core 3) tho Currcnpcmdihg valuo was0.u3u * 0.003. An ui}prcciable Doppicr cficct In 2MfJfitwlca wasAtdinud u!ily in tile suftest iqwctrum, in which tho mcqaurcd Iq-crease in fisbitin rate m heating from 320 to 1470”K waa 0.007 *0.003. (autid (Sweden)

35651 STUDIES OF THE KIPPI,ER COEFFICIENT AND HEKREACTIVITY EFFECT OF PVLYTNENE IN SOME FAST REA -

TOR SPECTRA, Tiren, L. L; Gustnfesart, I.; }fellstrtmd, E.:Haknnsson, R. (AB Atomenergt, studavfk, Sweden). pp 143-70of F ant I\eactor Physlce. Vol. 11. Vienna, Int ernatloned AtomioEnergy Agency, 1968.

From Symposium on Fact Reactor Phyeica and fl~lated Safety “Prohiems, Knrlsruho, Germtmy. See STI/PU~-165(VOL2);CON F-671 O43-(VO1.2).-. .- . . ..—,.

The Doppler brondonin~ of the 238Ucapture and the 235Uflsston ,cross -scctlons in fnsl renctor spectra hue been studied by irra-diating heated foils or pIatcs of the isotopes of interest in a kmallfurnace at the center of the qero-energy fast reactor FRO. Theexperiments hnve been applied to cores fueicd with 20% enricheduranium and diluted with graphite and pdythenc. .Very thin piateoof the different core mntcriala have been tmcd In n rcglon. sur- :rounding the furrmi’c In order to minlmizo hctcrngenclty cffecte. iThe mrnnutcd qunntlty in the {iiffrrcnco In the lnduccd y-nctlvltyof samplcn irrnd[8tcd at ambtcnt temperature nnd at tcmpcraturea iup to 1500 C. The effects of vnrylng snmp16 thlckncsa nmi of scat-:tering In tAe furnnce wall hnve ,aiao been etudicd. Mcnmtrcmcnts ,of the rw+ctlvlfy effect of pnljthenc have been made In two ~0 Iassemblies. The neutron spectra of the cores were broadly simi-lar to tho~e of current steam-cooled faat reactor concepts. Thee.xperlments include a study of the epatial distribution of the re-actlvlty coefftcicnt of polythenc. The results nfe in reasonableagreement with calculated values. ‘The latter are’sensiiiye tosmall changce in the absorption cross-section in the low neutronenergy range. Most of the calculations have been made with aone-dimensional dlffuslon theory p’mgram bsi:g 16 energy groupsbut a two-dimensional ce’de and a transport theory code’ have aleobeen used. Adcfit[onal measurements have been made on verticalpolythene rods, 2.2 and 4.6 cm th!ck, inserted In the central fuelelement. The measured distributions of the fission rate in ‘5U andthe capture ratce In ‘Shin, t! S1nand 1J?Au tna[de and around the rods

have been compared with results of multigroup calculations. (aufh)

75

.

a

VI. LABORATORY SUMMARY REPORTS AND MISCELLANEOUS

23534 [AFL-7246) PHYSICS DIVISION SUMMARY REPORT.Annual Review. Aprlll, 1965-March 31, 1966. (Argonne NationalLab.. lll.l. Contract W-31 -109 -eng-38. 180P. Dep. mn. CFSTIS.!.00 cy. $0.65 mn.

785b (ANIF72S5) ltEAC”~Ol{ lIEVELOI’hlENT l’l{c)GIMXfPl{(XltESS ltE[~Ol{T, SE1>”l’i;\Il\k:lt lLwti. (.irgwsnc IG~liws:il Lab,,Ill.). &.~. ~ti, l(jtj~o Contr:tct W-31 -ltJ9-cng-38. lUIII. fJcp.11!11. CH’11 S4.00 cy, $U.75 mn.

Summ:iric.s of prugrcas arc presented concc, rning tht, fIfl\l’R ,@rccyelc program, EIIR-H op~,ruti[m und tk{t,lul]mcnt. i)h)sics ex -Ix. I’lm,vIts in ZPI{-3 wuJ Zk’1’1{,burnup mcasurcmc,nl~ fur fast re -:lCLIII’S,Na technology, fuel development und procc.bsuig. rcaclorI)hysics dcvc.lq]mcnt, fuels and cladding dcv~.lul~nwnt mul fal]ricfi -tiun, hc,:it lrwrsfcr and fluid fluw studi(. s, mcuh:tnics (If niuIt”rlalsbtu[liern, Iluortdc volulillly prutwss d’c\clqm)u IIt, lIt~ld I:IUIU1dire,.1C(IIILL!I>I1811KLWBUIIII’ rt”s~ws’t.ll’, AAlt R dL’bfgll .md dC&\C]OIIIIILml,umt ,rescwrcb nn nuclear tsaf~.ly. (J.ll.ll. I

12231 (ANL-7267) REACTOk development PRO-GR,\M FROGRESS REPORT, OCTOBER 1966. (Argonne Na-t!onal Lab.. 111.). NOV. 22, 1966. COntract W-31 -109 -enS-3g.9Rp. Dep. mn. CFSTI $3.00 cy, $0.65 mn.

Measurements of the uniform temperature coefficient of reac-tivity of the fully loaded EBWR core with eight spike smsbmhllesin the first shim zone between room temperature and 360”F weremade with boric acid concentrations near 6 g/g~. TfSU~emPera-turc coefficient 1s pesltlve at ldw temperatures, becomes verysmell as the temperature is ra{sed, and apparently becomes nega-tive before 360° F Ie reactted. With planned modifications andmaintenance on EBR-fl completed during the recent scheduledshutdown, Run No. 22, projected for 1000 MWd, was begun onOctober 21. Almost half of this run waa completed at month’s end.Thirty-two of 54 total plllng foundation holes for the ZPPR werecompleted. The floor slab and foundation for the vault-workroomand service floor of the support wing were poured. Detailed re-ports of measure!pents made in ZPR-3 during the last four monthoon Assembly 48, a large, clean, plutonlum-fueled core, were com-piled and a aummasy la presented. The AARR Title I report wasaubmltted to the AEC for apnroval on October 7, 1966. T%e AAR.R

,core design waa changed to a HFIQ type, and all rcaearch and de-velopment work on the stalnleae steel cermet fuel wae terminated.

139ib (At4Jfi7279) REACTOR DEVELOPMENT PROGftAMPIKsGitESS REPORT, NOVEMBER 1966. (Argonne N*tlwsiil Lab.,lll.). Dec. 21, 1966. Contruct W-31 -109-eng-38. 98p. Dep.mn. CFST1 $3.00 CY, $0.65 mn.

Items of slgnificint techmcal progreaa which have occurred [nbotb the sptwiiw reactor projects and the general engineering re-search and dcvclopmtmt programs are tmmmarlzed. Programactivities are rc,portcd under five broad catcgoriea: Plutoniumf-l{lllz~tlt>n, Liqu{d-hIelill Fast Breeder Reactors, (ienerid l\cwc -tor “hchnology, Advtmced Systems Rwm!arch and Dnvelopmcnt, andNuclear Safety. Tbe ExperlmentsJ Boiling \Vater Reactor Pu re-cycle program is discussed under Plutonium Utlllzatims. Liquid-h!etzl Fas~ Breeder Reactors includes the Eaperlmental L3rcederReactor-11 operations, fsst zero-power asaembly development, andfast reactor physics, components, and fuels development. GeneralReactor Technology eaaminea applied and reactor physics, fuelsand cladding, engineering, chemistry, and chemical separations.The Argonne Advanced Research Reactor development is summa-rized under Advanced Systems Research and Development. NuclearSafety activities include coolnnt dynamics, fuel meltdown, mate-rtals behavior, energy transfer, Pu volatility studies, and TREAToperations. (H. D. R.)

13947 (ANL-7286) REACTOR DEVELOPMENT” PROORAMPROGRESS REPORT, DECEMBER 1966. (Argonne National Lab.,111.). Jan. 26, 1967. Contract W-31 -109-eng-38. 92p. Dep.mn. CFSTI $3.00 cy, $0.65 mn.

Items of significant technical progress which have occurred inbeth the apecl[ic reactor projects and the general engineering re-search and development programs are summarized. Programactivities are reported under five broad categories: PlutoniumUtilization, Liquid-Metal Fast Breeder Reactora, Generaf ReactorTechnology, Advanced Systems Research and Development, andNuclear Safety. The Experimental Boiling Water Reactor Pu re-cycle program is discussed under Plutonium Utilization. Liquid-hIetsJ Fast Breeder Reactors lncludei the Experimental BreederReactor-Lf operations, fast zero-power assembly development, andfast reactor pbysica, component’s, and fuels development. GeneralReactor Technology examinea applied and reactor physics, fuelsand cladding, engineering, chemistry; and chemical separations.The Argonne Advanced Research Reactor development is Sum-snarlzed under Advanced Systems Research and Development.Nuclear .%fcty activities include coolant dynamics, fuel meltdo~,

, accident analyses, energy transfer, engineering safeguards ays -tema, and TREAT operations. (H n n ~(auth) .. -...., .

77

1967 Laboratory Summary Reports. ..

21755 (ANL-7302) REAcTOti DEVEL0Ph4EtiT’PR% RAM , ‘ 23589 (ANh7308) REACTORD EVELOPMENTPROGRAM .PROCRESS REPORT, JANUARY 1967. (Argonne National Lab., PRC43RESS REPORT, FEBRUARY 1967. (Argonne Nat!onal Lab,,111,). Feb. 24, 1!)67. Contract W-31 -109 -eng-38. 106P. Dep. 1~.). Mar. 28,.1967. Contract W-31 -109 -e~-39. 106p. Dep. .mn. CFSTf $3.00 cy, $0.65 mu. mn. C FST1 $3.00 cy, $0.65 mn. .

EBWR has been owratlnrc at a rtteadv enwer of 42 MW since Regular and special fucI pins were rernovcd from the EBWR forNovember 11, 1966. - The r~actoo will ~e”shut down [n February . analysts of epcciflc Ieotnpce. The fuel In the pIutrmlum zone had1967 ao that apecisf fuel pins can be removed for isotope analy- , an average expoeure nf 1300 MWd/tOnne. A detsilcrf siudy to de-sis. In prepaxatlon for Run No, 2S, tbe EBR-11 corb sizo waeincreaaed from 81 to 91 aubsssemblies.. Since the enlsrg

&core

bas moved addliional driver fueI oui (o Row 6 locat ione, iquestion of relatively hig~ gamma hepting in blanket Rowe 7 and “,8 has seaumed new im~rtance. Therefore, detailed calculationsof expected temperature and examination of bl~nket eleinentaand their contained depleted U which ha$e achieved varying de- [green of burnup are being made before initiatin~ Run No. 25. Inaddition to routine proccseing and fabrication of fuel eubasaem-biiea at the Fuel Cycle Facility an Argon Cell electromecbanicslmanipulator was repaired in-ceil, with apccial tools, and an AirCell crane trolley which waa transferred tb tbe cell rwf encioeurefor repair. The Mark-fB modified fuel restrainer was testmf witha new ihinner abank. Fabrication of 3 experimental subaeeembliea,7 special subaaaembiies wiih the matrrisis therein controlled forIater evaluation, and 6 .subwecmblice of tho h~if-worth typo forUPC In making reactivity adjuatmwie in, tho rcwtor Sre aleo re-ported. Experi~eni8 were conllnucd in ZPR-3 Aescmbiy 48, aPu-fuelml criticeI ssecmbiy with a distribution of materisies!m[lnr to a large carbide reactor. Tbie aaaembly 1S being usedto make meaeuremente relevant to ihe FF l’F deelgn. Heterogmte-Ity messurcmente were made using thin 21SU, ~38u, arxt manganesefoils In neverai configurntlone. RciOtlve 2mU capture rate ,waemvmured at seven fxrnltkrrm near tbc coro mifiplane, ueing amrthod developed at ZPR-3. Excavation of the ZPPR rcaciorplt !s complctc. The six reactor pit poete have I>cen steel cappedarsl thr cnncrctc 10PS for thnm hnve been pnurcd. The AFSRrracior pii nnd room foundatinnn hnvc hccn poured. Placementof atrurtural aleel for Chc nuppert wing is 95% complete. Theprecnni cnncrete floor of the mqqrori wing in in plnce mxf allWII11O●nd @upport colunrna of thr vrmli, workrwm, end insideequipment rooms have hcen poured. A supplement to the AARRPreliminary Safety Analy81e Report wan completed, (J. R. D.)

,, ,,

tyrmine ewcliing in the uranium nnd cfrrrelatlon nf this to expo-sure time and tempe,raiurc was made. Ncutrrm flux wire irradia-tion wae cnnducted at Inw pod.ere to obtain distribution rates of -fiseion and plutonium productirm in the radi~i blanket. Radiaf

‘ blanket eubsseembliea of the Fuel Cycle Facility reactor wereexamined for external and internai change in physl~al reperties.

rFoil Irradiations were ,us,ed to measure the rcistive 23 U captureand fission rates and ‘% fission ratee in ZPR-3. Further studieswere also made to dcierm!nc the effect of the dieiortion of the

.fIux distribution on the iincarity of k,f~ subcritical measurementin reactors with a snftcncd neutron epectrum. [n ZPR-6 the ef-fecte of Na voiding on the fieeien dcneitiee in ‘SU and 23:U and tbocapture detwiiy d 238Uwere Investigated by foil measurements.

. Matcrisi earn Ie worthe and Doppler coefficients were measured/’for 23nfJand 2 ‘U in the fiPR~9: thcee rceufts are lietcd in tabular

form. Consimction nctivitiee are dctalfed for the ZPPR. Three,syeteme of fifreion-gas preaaure.transducers for the FFTF arediscussed. Foiled fuei detection methods. sensor leads for fluid,.-airmnls: in-core fiowmeters. and fuci-nins are some comooneot Isy%terns which are briefly” disiuseed. irradiation of U-~ aliey,fuels is discuss@: ceramic, cerm#. and mixed-carbide fuelirradiation ie also diecuased. A method for the preparation of .(U,Pu) C fuel 1s given. Development of refractory- metaf alloysfor eervicp in oxygen contaminated eyetems ie detailed; corroaimof jacket and structural materiale by Na, in the reactor is ex~-ined and results presented. hficrohardnes.a teats were made on “Ni-beae aUoys; results are presented. A relati~ely detailedoutline for fact reactor fuels is given. fn the area of generafresearch and develepmcnt the following topics are dfscuaaed:fast reactor coro-pararneter study. uses & 2SSUin a fast-reactor “era, neutrordc Inveatlgationa, thermaf design studies, and fuelcycle coste. An oscilloscope diepiay for an on-line computer is .described; changes in the crose section computer programs aregiven; reactor parameter calculations are discussed in some de-‘trdi: fuels and materista development are discussed at length: “radiation damage to structural materisie is outlined: techniquesfor fabrication and testing of fuels are presented. Various phasesof engtncering development are dfscussed in some ,detail. Resulisof corrusion studies for the Argonne Advanced Research Reaetor

,secondsry coolant loop axe tabulated. A general discussion of tfmreactor phyeice meaeuremente end expert menta in the AARR isgiven. A survey 0[ work done in nuclear ssfcty is gl,ven: the follow-ing subjects are covered: linkage of heat transfer and two-phssacoolant flow nodules, Na expulsion, superheat, critical ffow,electron-bombardment heater tests, convective instability. ther-mophysicsf properties of Na, component dynamics, transient topile loop experiment witii EBR-R Mark I fuels, summary andAnsiyeie of eingle-pin results, eeven-pln-cluster Na loop emrt-mcnte, vacuum-inert gas ftinvcbox. TREAT eprrat{nns. metai -waier renctione, nmf Po volatility s.nfciy. (M. L.S.I

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78

1967

30093 (ANL-_7317) REACTOR DEVELOPMEti P’ftOGRAM”“PROGRESS REPORT, MARCH 1967. (Argonne National Lab.,111.). Apr. 28, 1967. Contract W-31 -109 -eng-3fi. 124P, Dep.CFST1.

The EB\VR waa operated at the meximum permissible powerletel of 70 M\V. During the approach b Pcw3er, pile-oscilJntor !mecsurement8 of the resctor tranefer ‘function were made at 28,38, 49 and 57 hlW. In preparation for Run No. 25, severaJ zero-pwer reactor runs were made to obtabs measurements of reac-tivity worth of the stdrdese ateel suhaesemblies in Rowa 7 and8, which have replaced sutmsserhbliea of depleted U. An extemslveprogram of anaJysis ‘was initiated to determtne the sourceeand ,extent of Cu found f.n the reactor primary Na system. Removalof the Cu electrodes associated with the auxlJiary primary pumpshowed that the exposed Cu ends were severely pitted and erodedand had indeed lost Cu to the primary Na. The exposed Cu endsof the electrodes were sheathed in stainless steel and the elec-trorfcs were reinstalled. The pump was checked out and is operat-tng satisfactorily. Analysis for further sotwces of Cu irt tho prl:mary system 1s continuing afid resuJta are being evaluated.Pofitirrudiation emmfnation of radial-blanket subassemblies ‘from the 7th, tnis, 9211,and 12th rows of the reactor revealed thatlength, diamctral, and density Increases were greatest for theInnermost rowe, decreasing along the radius from the core, withno significant increiises noted for the 9UI or 12th row subaebem- ‘blies. Concrete for the ZPPR.cell ftoor and pit and for the blanketstorage room floor wee poured. Experlmente are in pro~meaa withZPR-3 Assembly 48B, a reactor with a two-zoned Pu core andwith a 124 15-in. centraf region that contalna Pu with 22% 2@qsubstituted for 4.5% 240PU. Critical masa was determined aftercontrol-rod catibratlons were made as well as measurements ofthe worth of core-edge material and of fuel spiking of the w+fetyrods. In the h lgh-Pu-content centraJ region, measurements weremade of Na substitutions, flsaion ratios, perturbatioti reactivitymeasurements with small samples, and of ffne flux variationsacroas the cetf. 23% fiaeion ratios were measured versus ‘s%,234u, z~u , 238jj, 21UPU,and 240PU. ReactiOn ram trsvOrBee were made

tn a ruhal direction at the core mldplane and reactivity travereeshave been made In the rudhtf direction us~ng stabdess steel, Ta,10fj 23:lj z~~pu a,,d 2WJ. IWO* on an improved proton t’tiCull n2wI-!,,tron spectrometer 1s also reported. Work done tn define morenarrowly the ~imitt! of precision of ZP[{-3 eaperimente by refine-ment of measurements related to tho ZPR-3 gap bd..erface i12re- .ported. (J. It.D.~

34076 (AN L-7342) REACTOR DE\’EfX)PMENT PROGRAMPROGRESS R.EPORT, MAY 1967. (Argonne National Lab., Ill.).Contract W-31- 109-eng-38. 139P. Dep. CFSTI.

Summaries of progress arc presented concerning the EBWR Purecyclr program, EBR-11 oprration and shutdown, physics experi-ments in ZPR-3, development of Z PJ?R and AARR, burnup mea-surements for fast reactors, Na technology, fuci development andprocessing, reactor physics development, fuels and cladding de-velopment and fahrlcation, heat and fluid flow, fluoride volatilityprnc..s drvclopmcnt, liquid melal direct conversion generator re-search, and research on nuclen r safety. (.J.C.W~) .

Laboratory Summary Reports. .,

‘44932 (At4f~7371) RE’ACTOR DEVE~PMENT PROGRAMPIKICW:SS Rk:J~(mT, AUGUST 1967. (Argorme Natlond Lab.,J1l.). .Sept.28, 1967. Contract W-31 -109 -eng-38. 126P. Dep.,C FSTf,

. . . . . . . . .. . . . .

. . .

REACTIVITY —measurements In EOI{.-JJ sore. rfftwin of ouwerlevei on; perturt,ntlon meauuremnmu in ~J41L:l, u*6 of a.mall -samplos for central .

.,. .CRITICAL ASSEMBLIES-flssIon ratio measiure”mkttts for urit-

nlum isotopes In ZPR-3, central; neutron spectrum in ZPR-6,effects of eodhim’ voiding on; fission ratios fnr urrinfum andneptunium In ZPR-9, measurements of; pressure veaael forZPPR, safe’ty factor txdculations for ‘

FISSION —ratio measurefients In Z PR-3 of uranium 233/ura-nium 235; ratio measurements in ZPR-3 of uranium 234/uranium 235; ratio meas~rement,s in Z PR-3 of uranium 236/uranium 235; ratio meaeu~ements In ZPR-3 of uranium 238/uranium 235; rat.i~s for uranium and neptunium, measure-ments in ZPR-9 of

URANIUM ISOTOPES U-238 —foii activations in ZPR-3; fissionratios for, measurements in ZPR-9 of

..-

. . .

NEPTU~RIM lSOTOPES Np-237—fission ratiou for, measure-met,t& In ZPR-9 of

. . .

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79

Laboratory Summary Reports. ..1967

30091 (ANL-721O) REACTOR PHYSICSDIVIS1ONANNUALREI’ORT, JULY 1, 1965 TO .JUNE 30’, 1966. (Argonne NatlonatLib,, 111.). fh’c. 196f3. Contract W-31 -109 -eng-36. 446p.[)ep. CFSTI.

Brief descriptions of work on the following subjects are pre- ,scntcd: f[sslon propertlrs anrf CPOE.SSCCUOOdata including fastneutron scnttcring studies, elastlc neutron scattering from ele -mcnls of Intermediate weight, elastic neutron scattering fromMg and S1, fast ncutr~n scattering from nuclei In the maarr regionA - 95-13% ~c intcrnction of fast neutrons with the 162; 184, and]$6 isotopes of \V. n smrch for fluctuations in the fission crossc.ecllon of “ftl, neutron flux measurements in the 10-200 keV re-gion, (d.n) strlpjdng rmctione, fast neutron total croes sections ~using n monoehcrgctic eource and canautomatic facility, fast neu-trnn energy tiegradatlon through the (n,yn’) process, unitary modeisbf nuclenr resonance reactiona, the ‘J2Cf fission neutron spectrum”from 0.003 -15.0 hieV, direct and absolute measurements of aver-age yield of neutrons In the thermai fission of 23tfJ and spontaneousfission of 32Cf, spontaneous fission hnlf-livks of 24;Cm and 2t40 Cm;thermal reactor physlca including High conversion, (Hi-C) critical ,experiment, Hi-C uniform lattice calculations; initiai cr[ticai ex-periments of the EBWR Pu recycie pro ram, measurement of

Ecapture -to-fiaeion ratios of 239Pu and 2 Pu in the Pu Inadtng ofthe EB\VR, tent rol rod evaiuat ion for thermai and intermediate , ,reactor8, smrrii reactivity measurements to the Argonne Thermai ,~urce Reactor fASTR), neutron beam epectra extracted frOm the ‘,High Fiux irradiation Reactor, Argonne Advanced Retrearch Reac@fAARR) critical experfnmnta-preface, AARR critical experiments-cootrol blade wortha, AAHR critical experimenth- prompt neutroniifetime meaeurementa by the Roesi-aipha technique, ~ criticei ,experiments - Cd ratio measurements, AARR critical experimenta -actiration and power distribution measurements, AARk critical ex-perimmrta - vnid and material reactivity wortha and temperaturecoefficients, #WRR critical experiments-beam tube experiments,AARR critical experiments- startup source requirement andinstrument reeponse, AARR Calculations- preface, AARR cal-cuiatlons-analysis of the critical experiments, AARR calcula- ,tiona-,generaf reactor physice deaigrt anaIysia, Am caicu-.iaiimra - reactor physics charatteristice of the ITC, AARRcaiculationa - factors in optimization of experimental fiuxea,AARR calculations- ehield design anaiyaia, AARR caiculaiione-aaaiysea of hypothetical accidente; faat reactor physics includingihe ueutron energy apcctrum in a diiute UC-fueled fast ‘critical

4

●s ~bly, neutron epcctra in depleted U, caibuiatione of Na-voidc licienta in large faat neutron carbide cores in asaemblieeNo. 2 and 3 of ZPR-6, caicuiationa of the effect of thin elab het-erogeneities on tbe non-leakage reactivity component of Na void-ing, non-iinearity fn ths apeciral compnncnt of Na void effectas a function of Na content, effect ,of parameter uncertainUee onNa void effect and criticai size of faat reactors, Doppier-effectmeasurements on a diiutd carbide faat aeaembiy - ZPR-6 aeaemblyNo. 42, mcaaurcd phyaica par~etere in a zoned fact UC core-”ZPR -IV asaembiy No. 42, analyeia of the uncertainties in theinterpretation of zone Ioadcd experiment, measurement of theBL-Qtialdttr[ribution of thr importance of fiselon neutrone in ZPR-6arwmmhiy No. 4z, etarrctard deviation of ion chamber current mca -e.urcmenta in ZPR -6 nsar.mi)iy 4Z, measured reactivity removairatra in ZPR -6 assrmbiy No. 4Z, the Argonne Nationaf Laboratoryof ZPR-3 atraembiy No. 48, criticai assembiy comparlacm colcuia- ‘Uona uahrg new crrma section data, comparative nrutronic charnc -teristica of metal, oxide and carbide EBR-if driver fuels, the effectof furi and biankei changr.e on !ho LuR-11 flux, FARET Core I fuelirradiation program Mnrf rofrrcncc IibBlgrr, twenty-six group croaasection awl for W. baaed rockci systcma, phyaica measurementsin (as; W rocket reactor criiical cxpcrtrnenta, measurement ofapce -drpendcnt matrrini wortha In eeverai ZPR-9 acscvnbii.ca,rockrt orlticai sna-mblies snaiycis, phynicc meamtremcnts itI nn -

. .

---- . . . -.opcratii~ fact brccrier power reactor, fu;ther ncutronic atudlen

.

of the 1000 MW(C) mcfni-fueled fast breeder reactor, reactorphyaice cnl,:uiatiorre for a 10,000 MW(UI) fast Nd-cooled bmcder,fast brccckw rcnciom fnr water dcaaiting, criteria for the rienaityof monitoring points In iarge reactors: fast reactor aafcty inciud-ing cxqpabllitics of the present TREAT fnciiity core aa a fast [iuxloop meitdown fac:iity, mcltdewn expmlments using the Mark I in-tcgmi Na ioop, analyses of sirrgie pin loop meltdown experimcnta,properties of Irradiated UOt pins prior to TREAT faciiity tran-sient, photographic faat reactor eafety experiments on irradiatedoxide pins a’f the TREAT faciiity, traneient +n-piie teeta on U02- Wccrmct rocket fuel eampies, dcelgn of the Mark R intograf TREATfaciitty Na loop, calihraiion mockup for the iarge ioop ICS1 sectionfor the TRiZAT facUity, tranaient reqxmae of etand-off prceeuretranmiucer aeecmbiiee on the TRF;AT facUity integral Na 100pa,extensible multi-purpose vacuum glove box, cxperimenial reeoltoand Irnprovemente tn the fast neutron hodoacope, the exact tirree-dimenalonat eolution for Urermoeiastlc otressee and diaplaccmcntain finite and infinite tubca, traneient vaporization of Na in reactorcoolnnt channeis, convective heat or maes transfer with phaeechangea, theoreUcai prediction of thermodynamic and transportpropertied of mctd vapors, equation of state of reactor materialsat, high pressuren and temperatures, a modified equation of etatefor hydrodynamic calculations in the AX-1 numerical program,propertied of refractory ceramics at extremely high tempdatures(UC ilquid expansion), modification of the high temperature Wftiameni furnace, faiiure preseurea of thfck-walled doubiy-reln-forced concrete oel~s, maximum permieaible body burdens ofPU Lsotopen and reeuiting reieaee criteria, fast reactor meitdnwn “accident analyeis ~ode, PREA~ experimental phyrrica techniquesand facilities inciuding a low geometr a counting chamber, abao-

1lute” determination of fieeion rates in ‘fU and 2*U and capture, ratea in 2MU by radiochemical technique, precision fission rata

rncasuremcnts by f!ssion track counting, soiid-etate Comptonspectrometer for measurement of reactor y epcctra, feedbadtrstabilization of nuclear countirig channel a, signal ❑piitting intofact and sio~ charmele, design and construction of an fmproved

f Mn bath counting ~yatem, low flux measurement of 2JhJ epicad-mium capture-to-fiesion ratio, reactor re8@rse to an oaciitat@g

I neutron source, neutron fluxee required for activating probe1 materiaiia, a code to permit fieeion product decay corrections

withot+t the uae of a reference foii, determinaUon of the k-con-: atant for the Dy eubstitutfon method, additional calculations of

the activation of spheres in a nonisotropic neutron flux, uee ofa small digital qomputer in data analyeis and control of criticalfacilities, a Ge(Li) detector system for the measurement of y-raye following inelaatic neutron scattering, a multi-angle faatneutron time-of -flight eystem, multiple angle detector apparahrcfor neutron elaetio scattering and polarization meaaurementa,m!.tltiple scattering correction, automated computed controi ofa fast neutron iafxratory; reactor computation methods and theoryincludlng Ure Argonne Reactor Computation fARC) eystem, theARC system glossary, the Multigroup Constants Code (MC2),

.

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80

1967modiflcatioh of THERMOS to generate ‘transfer cross sections,generation of multigroUp croaa sections using a coupled MCI-THER~lOS code, variation of thermal croaa oections with buckitngin conclatent PI and B1 calculations, development of a code tmstudy furl m anagemcnt, AMC - A Mohle Carlo code, developmentand mmlysis of Monte Carlo methods, quasistatfc treatment ofspace dcpcndcnt reactor tranaienta, apace dependent kinetic cal-culations using the WIGLE code, reactor systems analysia andhybrid computere, computation of the coupled error function byoontinu ed fra ctiona, treatment of source dtacontinuities In thesolution of the diffueion equation, revision of the bulk shieldingcode MAC for tho CDC-3GOO computer, codes for analysis ofelastic acntterhg angular distributions, multilevel croaa aectlona’for a flmslonnble isotope, the effect of interference on the reso-nance ‘Integrrd mixtures of Th and U, the effect of randomness jon group cross sections, the chemical binding effeci~ on theresonance llnc ahapea of 2WU in a U02 lattice, equivalence be-tween homogeneous and heterogeneoua resonance integrals tncyllndrlcnl geometry, effect of the fluctuations in colliplon den-aiiy on fast rcnctor Doppler effect calculations, an approximatecnlculntirm of space dependent flux uelng a varlnllonal principle,neutr,>n-wn!,c analyais: mlaccliancoue lncludin~ mwrgy epectrumnf rnflt cORmlc-ray ncufrona near sea level, a U02 systcm fordlrcct conversion of nu$lear energy to coherent laser light. the-nry of plasma onclllatlone -grncratlon of thcrmlrmlc RF energyand Interactlona with DC, clrculnllng shlcld reactor for npacepowf. r, #rid improvised shutter dcnlkn for the JANUS ret+clnr.A tofnl of 609 references is Iiated thrmt~hout the repnrt. (M,L.S.)

Laboratory Summary Reports. ..4693b fBNW”~501)FAST FLUX TSST FACILITY, @w- ““terly Progreaa Refmrt, January-Mmch 1967. Aatley, E.rf.fBattelle-Northweat, Rlchld, Waah. Pacific Northwest Lab.).Apr. 1967. Contract AT(45-1)-1630. 202p. Dep. CFSTI,

FAST FLUX TEST FACILITY—experiment facilities for,, de-algn of; deslgna for, evalurdonof various; reactor core con-figuration for, evaluation of split wedge and conical; elcctri-cnl supply systems for, schematlca for external; heat rtimovalsystems for, process dtislgn conditions and construction coatafor; coroputer simulatlona of, digital andanalog; cmlnnt cir.culation in, analog simulation of natural; atructuraI materialafor, radiation effticts, on; materials propetiie~ hwrdbook for

HEAT TRANSFER—bent removal systems for FFTF, evalua-tion of

LIMPS- dealgn of closed teat, layout atudiea forREACTOR FUEL ELEMENTS-reroute handling of FFTF, ,

eval uat ion of gaa -cooling system for; examination fact] it iesfor, design of FFTF; thermal nnalyata of cooltint flow block-age itt FFTF; cladding for FTR, radiation effccta on

REACTOR ID(PERIMENTAL Facilities-design parametersfor FFTF; heat transfer analyses for FFTF rabbit capsulea

FAST TEST REACTOR—core for, parametric atudics on;COOIIng systems for, mrulyaie of; tube materials for, atreaaanaiysis for; core for, hot channel factor determbmtion for;core for, r’adioieotope tmnaporf rate in driver

REACTOR CONTROL SYSTEMS—desl~ for FFTFREACTON FUE’fS-kadlntion testing of FFTF; neutron flux

and l,ower peuklng fatitorw In FFTF, parametric wmlyaes of;bumup cffticts on FFTF, safety tinalysiq for; cladding for~d>t, Wl]ySh Uf

N} l; ’rllflNS— flus distrihutlons in I.’FTF, evalu:ttl”!] of rmfitu-idt Llf ctfe(.’ts uf skcwcxj

TH1.l{MOCO(:P 1.1:S— time response ~f ungroumtud, analysis ofREACTOR SA1’ETY-scram requirem~nta for eingie channei

fu(.1 mt Itlk, wnRLAc’’f(m hl(JI)l:l{ATO IIS — ef fects on F FT F rwut ron physics

ptir;t!nctcrs of beryllium oxideU1{ANIIJhf ISOTOPEi U-23il— Doppler coefficients for, effects

of crystalline bimflng,onRF AC’I’lVITY-worthrn of controi rods for F~rF, two-

dlm~nsIm:,l lr:lnsr~,rf mrxfels for cnlculatl[m ofREA(.VYJH (:( INTI{(J1. 1:1.EhfE.’N~—rcactlvity wortl,s uf FFTF,

tw(j-~lllriut,sl,~ll:ll trunsport mwtclrn for calcultstiun ofSIIIt.l.I]l>:(; - ,;ilL.UISti(,”B for 1.f7TF

7885” (NAA-SR-12175) AEC UNCLASSIFIED PROGilAMS.Quartrrly Trchnical Progress Report, Jufy-September 1966,(Atomica International, Clmoga Park, Calif.). Nov. 25, 1966. ,Ccmtract AT(ll-1)-Gen;8, 173p. Dep. mn. CFST1 $3,00 cy,$0.65 rnn.

Dc~rclnpmonts arc rrported for studies on: stability and proper-ties of ciadding and structural ailoys in a high temperature, liquidmetal, fast neutron cnvironmenl; boiling atudics for sodium reactorsafety; fast spectrum Doppler measurements; Na compcneni dcvcl-opmcnt; sodium reactor cxbcrimcnt opr-ration; Piqua dcvclopmcnt;rcactur physicp; ”reactor fuels and mate riala; high timpcmturcreactor fuels, and matcriqls; Na chemistry; reactor s~fcty; fissionproduct and conLImlnatlon control; characterization of Na firmand fission prmhtct rclcasc; high temperature and radiation chcm-islry; clcclrpnic stmcturc of metals ,anr.1ailoys; and radiation ,damage in crystalline solids. (P. C. H.) .

81

1967 Laboratory Summary Reports. . .

405bi (NAA-SR-12395) AEC UNCLASS!.FIED PRC@RAMSQUMTftRLY TECHNICAL PROORESS REPORT, JANUARY-MARCH 1967. (AtomIcs International, Canogs Pat% CalIf.).May 31,1967. Contract AT(04-3)-701. 184P. DeP. CFSTI.

Dcvelopmcnta are reperted foratudies on: cross section anai-ysin: integral reactor-physics experiments: barric-theory improvemcnt; fast spectrum Doppler measurements: ~i.ting studies forsodium rcactoreafctjq measurement of Depplcr coefficienbxreactor d.ynamice eimufator development: fission product con- ,taminatlon control; characterization of Na firen and fiseion prod-uct releaee: fission effecta in metal fuels: Sodium Rearttcm Exper-

,Iment operation; refractory moderator materiale; FBRfdeldevelopment, fuel cladding, andatructural materials; coolantchemistry: materiais management; mechanical propertied: dy-namic loop teathr~ modca of failure and He degradattom, baaicpropcrtica of UC type fuele: NA chemiatr~ HNpF retirement:PN P F fuel elements; high temperature chemiatr~, radiationchemistry electronic etructure of metals and alioya; radiationdamage in cfyataiiine solids: and radiation, chemistry of chromo-somes. (P. C. H.) .

23711 (BNWL-340) . I{EA$WOR PIIYSK:S DEPARTMENTTECiiNICAL ACTI\’fTIES QUfUtTEltI, Y iWPCNtT, JULY-SE P-TEhii3Eil 1966. (ilattclic-NOrt.bwOBt, f{ichiund, Wabh. pacificNorthwest Lab.). Oct. 15, 1966. COntract AT(45-N-1630. 72b.CFSTI $3.00 cy, $0.65 mn.

A recent’ rwisicn in HRG (R&ford Reviacd Gain), a rtqutron‘oimving down codu, medifica the calcuintion of the offcctive reao-nancc integrai of Individual reaonartce by using’for normalizationtin upinwximation to the flux used in the resonance Intebmal calcu-lation itaeif rather than a l/E flux. A ctdcuiation study of ther-maiizatlun within n aimplo celi haa been made using the RBUMonte Carlo, THERhfOS, and Program S-XIII codes. A compari-son of the results Fhowa the RBU Monte Carlo thermal izatfonroutine ia formulated corroctly and free from detectable numc!ri.cal error. Experiments have bebn con@ctcd in the ~RCF using .2 wt % pu~ - UC+ fuel in H20, These experfmcntg are directedtowards determining the pilyaica properties of Pu-fueled H20muderated reactor ayfitema. Results are given for a two-zonecritical experiment. Also given are reauits of meaaurementa ins single-~one loading of fuel which crmtaina 24 wt % 240Pu. Acafculattonai study of therdiallzation in PU02- U02 fueled H,20moderated lattices has been porformcd, The purpose of the studyia to determine whether errors are incurred in making nssump-tiona pertaining to scattering procoasea; boundary conditions, andthe source of thermnl noutrona. Meaaurementa i)ave been mndein the PCTR with a mixed iattice’ ti Pu-A1 fuel and tfrorla target#’in alternating coils. New tecimiqucs were developed to adapt thePCTR type of measurement trr this iattico array uf auperceilb.The results includq values of k- for the nrray with Snd withoutwater cooient aurrerioding the fuel and ‘targeia, Neutrun activa-tion,of gold fo[la in the thermaf coiumn of the PCT~ have beenmade to measure the relativo neutron flux intensities for variousthermal coiumn conditions. The addition of a ppiyethylcne refidc~ ‘tor to the graphite stack was found to improve the thermal neu-tron intensity and to reduce the fast neutron component of thetotai flux. The pre6enoe d a amaii cavity in the center of thethermal coiumn did not appreciably rcduco thtr neutron flux gra-ditint in the standard foii irradiation position. Neutronica calcu-lutkxut were performed for dn 800 liter, PuOj- U02 FTR “refer-ence” core. Principal phyaica ~tatiatics and kinetics partimetersware determined. To esoesa the accuracy of the present croaa -scction aot in”uae for deeign caioulatlcma, numcruua critioal●aacmbly rfmuitn have been anal yz~d. In general, the computedfltisiiu fuel fitialmr ratioa are in reasonable agreement with ex-porlmwrt, whcrcns the computed 2~aU/ZSsUfission rutius areconsinkmtiy higher than experimental valueti. A new group cross.srxtirm “collapsing algurithm” haa bcon devised witici] makesuae of a pseudo ihaorptiun crww acction in each coarue gruup.

The uac of such “porturbaticm” truss aoctirms ltJ much mcwoaccurate for computing moderator rrmctivity coefficients thancorresponding mwielti u~ing flux wclgittcd sections. Tho rcnwaf-dlffusion code MAC imti iwon utiwi h> conqnrc ft,ur diff(-rent ,axieiahleid arrungement~ for tlw i’Tli. Energy und tqmtiul dtstrikutionsof buth neutron md gamnm tiuxea huvc km uidouwd. ffatiic shtcid:fng rcquirementa for a number of t’TH fuci procctismg tin~ imn-diing fucilitica have imwr specifiud Subcriiwtil m,utrun mtt,ractiunex$erlmtinta wero performed with bure and Piexiglti rcfiuctccl ur-rays of buttica cont~irdng aqucoua solution of 233U. The c riticainumbcra of Iwttlca in artwya were determined fur vuriuuu apuc-iqga. br additioa, thtr effects of internal mechwatirm bruugin abuutby poaitloning Lucite sheet in varieus thickncasos butwcen the ‘bottles compriaing,aeverat ●rrayit were atudicd. The oonce@ra-thm of U in the experimcnta was, 330 g 233U/iitur. Tho twperi~ments, provide duta for nucleur tiafety @dance in hnrrdting,storage, and ahipmont ~f the muterial mwf fur chtx, king interac-tfoa ceictdationa. A series pf qritictihty expcrimcwts wcrw bt’b~n,.uaing a vessel of unique design, fur rfcterminin~ Imre und rcficctedcritical thickr@scs of piutmdum aoiution in siab gcunwtry. Thoaiab veaael ,WSSde8i@Cd to permii n{ijustmcmt uf itti thiclowssovor tbu rsnge 3 to 9 in. Criticality csiwrimcnts were pvrfurmmf,bare und water rcfioctcxf, in iho tf, ichncsM rwrgo .i.5 tu G.fi in. withPU(N[))), tmiutirm ctmtnining --!jti g IJUjiiter with an acid moiarity

, of 2.3. fnfinito ul@ tilickrw~soti nrw OstinlatLd frum tiw ntcusuro-,mcnt duta. Tti pctmit ritudying the fuudamwrtul bcimvhw U( n@l-trunti in Pu-fuelcrt Nydcmti, crlticui npi)roicil, IIuiscd wolrurreuurce ued fuli actlvutiuq n,easurumwds WIIM nuulu im titrvuPu~-ptAystyrune-f uOimf a~rncmbl Ics. (uutll) - .

-.

/ 30103 --, fBNWL-4oo) REACTOR “PHYiI& DEP~Tf&f4T~EcHNfcAL ACTfVITfES QUARTERLY REpoRT, CJCTOBER,NOVEMBER, DECEMBER 1966. (f3attelle-Northwest, Ricttiand,Wash. Pacific Northwest Lab.), Apr. 15.1967. ContractAT f45-1)-1830. 66p, Dep. CFSTI.

Thermalization theory integral formulation ie preeented; 8ingleparticle wave futtcfions describing low energy elastiq scatteringby target nuclei of He and O are deacrib.@. A comfmter program,BROAD, for direct calculation of temperature dependent croeesections bas been written. Modification were made to UNICORN,ffRG, TEMPEST, ZODfAC 2, ZODfAC 3, and ZODfAC F. Thecomputer. t!ode OP haa been written ‘for shielding etudfes. fX3NVRTban been written to mnvcrt foii activation data from paper ta~ t~digital computer Imrgrmgc. Reactivity cecffir Iente are presented .for a PO fuciod light water rwtctor. A d(. acrlidion of Urc gammafacliity used to acquire data from Irradiated fuci clomcnls in

‘given. The doveioprnent of tho reactivity techniquo for dctcrmina-tlon of effective ~“l! concmdration in sflmplwa of boratcd D20 isdcrwr ibcd. no reaulte of criiicai expcrinvwts in the PRCF aro~ivcn. Result- from an cxtertaive eet of reactivity mommrcmentsof ncuiron abaorhing rndn in RIO1 -U02 -1120 Intticce aro sum-marlzcri. Thq worth of fho HTI,TH control rods are given. Com-pari80n8 of unzono(f and two-zoned concoptn for tho FTR aro

“ dcfniiod. Crystaiiino binding offoct~ on tho FTR ~ppier coofft-Cicnt nre dincttancd. FTR fool heterogeneity effocto are examined.Faqt reactor invoetigntione for the f?TR are pronorttctf. Reactivitymvneurement tachniquoe ueirtg puleed p~trone are dincvmmtf.

An.aiyaee of critic.ni exporimento in hydrogmrotm mcdla m+ glvvn.CryrrtaI epectromoter tttudico of ntomic anrl molecular motiorrn ofvmtvr at 26~K nnd 290”K are preacntcd. Cro.ee ecction datn forelow neutron inelastic scattering in H20 end D20 are prceentcd.

~ (M. L. S.).“

.

●

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82

1967 1968 Laboratory Summary Reports. ..

.

44830 (GA-7396] HTGR BASE PROORAM. ””QuarterlyProgress Report forthe Pericd Ending Au~st 31, 1966. (Gen-eral Dynamics Corp., San Diego, Calif. GeneraI, Atomic Div.).Now. 15, 1966. Contract AT(04-3)-167. 58p. Dep. CFSTI,

PRESSURE VESSELS-tcsUng ofhlghtemperature ifascqolcdreactor prestres.sed concrete

, REACTORS, GAS-COOLED—pressure vesscle for high tem-perature, development of prestrcascd concrete; fuel elernentefor high temperature, dmigm effects on reprocessing of; kl-netlcs computer codes [or high temperature, development ofspace-time; fuel cycle for high temperature, economics of

GAMhlA RADIATION— buildup In hctcrogeneoue media of, cal-rulatlon ‘of; flux calculations using tran9frcrt theory, effects ofquadrature on

fN-PILE LOOPS-fuel clement Irrndlntcd tn GAIL, postirradl-.atcd testing of.

RF.ACTOR FUELS—radlatlon effects on coated fmrf{clc, tabu-lation of G.AIL IV; cycle economics for high temperature gas-conl rrf; costlngs for, development of barrier; dtluent particlesIn. chcmi.sf ry =tudles of: irradiation of costed particle, re-Lnllts of

LTfAVllll fSclTf)P1’X l’-23q — reswrnnco nlmnrptlfm as a func-tion (If Intllro p~rxmotl.r~. I.:IlrIIl:Itim 01

nsslfj~ pfifl[,l,~.r$— tlcl,m.ltl,,n ,,n atoinlvw! .dre] sprclmenfrom GAI1 IV fuel vlomcrt; depo. illon In tdninlws ntcel pipedmanstrmm from GAII. Ill 1! f!!vl elcmrrd; rvlroso fromb~ryllln I!tcl compact ,,f N!”:l,l.v.~t:!t~ l!ns.~(~un

Fll ?1 1{5— rnrllocbernlcal nnnlynrs of GAIL IV mnln loop, re-Bu!t* (If

REA(”T(IR F(W 1, F.f.EM KNTS — refrroccnnlng of h,igh tcmpcra -tur~ gan-f oolwf, of[eets of furl clcvncnt dcnlgn on: reprccene-lng of hl~ temperature Ras-deoled, eeenorn!cs of

CO:\ ’fYNtiS—behavfor of silicon cm+dde rouctur fuel, cIfticts ofutrongly mwruslv~ Wotodphcre on; fhwlun prduct rclcawfrum barrier

NF [JTIMJN CROSS SECTIONS —evaluatlcm of umnlum 2“{’>PJ, U’f’(INIllM— diffusion tnudics onGrf/\llllITF — r~dlatlon effects at high tempermui us ,m; 11!11-

miil c~l,.u)s!vititis of isotropic and anlsotruptr (Ml. S.1

40674 (GEAP-5294) ANALYSIS OF THE SEF~R MUCKUfJCRITICAL EXPERIMENTS IN ZPR-3. Reynolds, A. 14.; Stewsrt,S. L. (General Electrtc Co., Sunnyvaie, CaJif. AdvanccLi i+xt-ucts ,~ration). Mar. 1967. Contract AT(O4-3)-WO. 5.tp.~D. CFSTI., For Southwest Atomic Energy Associates:

,,

A stwies of critical experiments were performed on a mockupof SE FOR at ZPR-3. Analyses of these experiments snd the applt-&ation of the results to the SE FOR design are discussed Criticalmass values were determined for 1-, 2-, and 3-segment SEFDRfuel designs to help establish the Pu atom fraction in the SE:FORfuql. Reactivity effects of axial fuel expsnsion wcru mi”ssurrdwhich Id to tielectlcm of the 2-sebm~ent clesi~ for SE Ft)R, Mcn -surements of the reactivity worth of the radial rdftwtor e>t:tb-Ilshed the adequncy of the SE FOR reflc!tor cold rfjl systuun. TheDoppler coefficityat was measured The calculutd ‘jdL! DupIIlcrcoefficient was in agreem$nt with the experlmunt; th~, nit,usurcd239PUcontribution tO the SEFORI Eoppler coefficient W’USncsr z(!rO.It warn demonstrated that the Sfl FOR Doppler is significantly morenegstive than the conservative value assumed fur S3f~b~Jr& mlal-ysls. The maximum positive rcactivlt y caused by loss U[ sudiumwa’s mensured; the mesaured reactivity was smnll (t6f I snd C“loscto the calculated value. The ratio of prompt neutrun Iiit,(imt, tudelayed neutron fraction was measured both by the puis{d n,.utrontechnique and by noise analysis. The values n]essured by IIW tw,>techniques were in agreement Fission rntius, fissl!]u ssd lMIrUntrsverses, and Pu wnrtb disirlbuiions wt,re nl.wwrv,l s!],{ i{rt. .uu\-parcd with calculations, (suth~

32734 (ANL-731O, pp 137-248) FAST ~EACTOR pHYSfCS.(Argodne National Lab., 111.).‘ URANTUhf LSOTOPES U-238—neutron cross sections for, ceL-

cuiated effects of resctor environment on absorption; fisetondensities br, sndium void effects on abaolute; neutron capturedensities in, sedium void effects on absolute; reactivity mea-surements tn ZPR-9 assemblies 11 and 12; reactivity worthdetermination fn ZPR-3

NEUTRON CROSS SECTIONS—calculation of uranium-238 ab-sorption, effects of reactor environment on

CRITfCAL ASSEhlBLIES— reactivity effects of uranium-238 onfast, comparison of measured and calculated; reactivityworths and expansion effects in fast ZPR-6, measurement of;neutron flux spectra in ZPR-6 snd Z.PR-9, comparison of reefand ad joint; Doppler effect measurements tn ZPR-6 endZPR-9; resctor dimensions and msteriai com~sltiona of fastZPR-9 assemblies 12- 17; Doppler reactivity measurementsin fast ZPR-9 assemblies 13-17; critical mase determinationfor large uranium csrbide fast ZPR-6; fuel loading pstternsfor uranium carbide fast ZPR-6; core for fast ZPR-13, heter-ogeneity effeets on; fuei loading in uranium csrbide fastZPR-6, sbsolute fission rates for bunched and unbuncheduranium-238 in; core for fnst ZPR-6, sodium void effects onabsolute fission densities in uranium-236 and uranium-235and capture densi~ in uranium-238; sodium void coefficientmeasurements for large uranium carbide fast ZPR-6; eo-dlum void coefficients for ZPR-6, effect of renctor environ-ment and inading pattern on; reactivity measurements inlarge uranium carbide fast ZPR-6, temperature effects on;cores for ZPR-6 and ZPR-9, mcseurement of central fissionrntlo in; core for ZPR-6, menaurement of fission neutrondensity III; design parameters for ZPR-9 assembllos 11 md12; cores for ZPR-6 and ZPR-9, comparison of calculatedrMd ead adjoh’it fluxed at centerline of; Doppler effect mea-surements tn ZPR-Y aesemt-dies 11 and 12; cores for ZPR-6,neutron spectrum compnrisona for zoned and homogeneousfsst; sodium void reactivity calculations for ZPR-6, heter-ogeneity effects On: neutron die-away cxperlmcnta in ZPR-8,tabuiatlun of results from; reactivity measurements In ZPR-8,puiscd neutron techniques for; neutron dccsy ccmstnnt mea-surements in ZPR-6, use of pulsed neutron technique forprompt; reflectors for fact ZPR-3, ssvings propcrtlcs oflnconel- sodium; core for ZPR-3, symmetry effects of em-bedded reflectors in blanket sround; rcactlvlty worth of. re-lation of reciprocal flux to; reactivity worths in ZPR-3, com-parison of rr!caburcxf and caicuiatcd; plutonium fission rates[n, calculation of

REACI’fVITY -effcctti of urmlum-238 on fast critical sssem-biics, comparison of measurcsf snd calculated; cffccte of ffs-eile material expansion in fast reactors, caicuiational pro-cedure for dcterminlng; mcmmremcnts in fast ZPR- 9ashembiiee 13-17, cffucte of temperature (In: mentmremcmte inZI)R-6, pul scxf rwutron tuchnlqut.s for; deL.rmlnotion8 forfast convcr~r renctora, efi~,ttb {,( rnodium voldlng on

URANIU.M OXIDES U02 —fuel pcl16ts of, temperature cffeCtSon radltd expnnalcm of axioi constrained

URANIU.M IS(Yr OPESU-235 — expwwion effects on fast ZPR-6reactivity; fibtikm [Iensitlcs in, sodium void cff[.ctti m al)sO -Iute; reactivity mcasuremwrts in ZIJIi-9 assemblies 11 and12; reactivity worth detcrminatiun in Z1)J?-3

.MfJJ.Y1jJJf’.NIJM —Dupi~lcr effuct mcasurcmtmts in ZPR-9 as-HemiJiies 12- 17; reactivity mcasurcmcnts in largu urmlumcarbide fsst ZPR-6; reactivity mcavurcmcnt~ In ZJ>I{-9 ns-scmblies 1 i and 12; rqiwtivity worth dctcrmlnution in Zl>i\-3

83

1968

TUNGSTEN—reactivity -meamtr&.ients “in lfige uranium carbidefast ZPR-6; reactivity measurements in ZPR-9 assembling 11and l% Deppler effect measurements fn ZPR-9 assemblies 12-17

NfCKEL-Doppler effect messurementa in ZPR-9 ssnembliea12. 17; rcactivlty meaeuremcnts in large uranium carbide faatZPR-6; reactivity meaaurementa in ZPR-9 assemblies 11 and12; reactivity worth determination in ZPR-3

TA!!TALUhf —Doppler effect measurements In ZPR-9 aasem-blica 12-17; reactivity meaauremente in large uranium cer-blde faat ZPR-6; reactitfity messurementa in ZPR-9 asaem-bllea 11 and 12; reactivity worth determination in ZPR-3

lRON-Doppler effect measurements in ZPR-9 asaembliea12- 17; reactivity measurement tn large uranium carbideZPR-6; reactivity worth determination in ZPR-3

CARBON-Doppler effect measurement in ZPR-9 eseembliee12-17; reactivity measurements In large urmium carbidefaat ZPR-6; reactivity measurement in ZPR-9 aaaembUea11 end 12; reactivity worth determination in ZPR-3

SORON-Doppler effect measurement in ZPR-9 assemblies12-17

STAINLESS STEEL—Doppler effect meeeurementa tn ZPR-9assemblies 12-17; reactivity measurement in large uraniumc srbide Z PR-6 on Type-304; reactivity measurements inZPR-9 assemblies 11 and 12 on Type 304; reactivity worthdeterminniion b ZPR-3 ?f TYP? 301

ALUMINUM —Doppler effect meaaurementk in ZPR-9 aiaern=blies 12-17; reactivity messuremenia fn large uroniumcarbide fast ZPR-6; reactivity meaaurementa in ZPR-9assemblies 11 snd 12; reactivity worth determination tnZPR-3

BERYLLIUM-Doppler effect measurements in ZPR-9 as-semblies 12- 17; reactivity measurement in large uraniumcarbide fast ZPR-6; reactivity meaaurementa in ZPR-9 ss-aembliea 11 and 12

ETHYLENE POLYMERS — Doppler effect measurements fnZPR- 9 assemblies 12:17; reactivity meaauremente in’ largeurmium carbide faat ZPR-6; reecilvlty measurements InZPR-9 assembiiea 11 and 12

S4)D1UM— Doppler effect measurement in ZPR-9 assemblies12- 17; reactivity measurement in large urenlum carbideZPR-6; reactivity measurement in ZPR-9 asaembliea 11and 12; reactivity worth determination in ZPR-3

PLUTONfUM —Deppler effect meaauremcnts in ZPR-9 an-aembliea 12- 17; reactivity measurements in large uraniumcarbide ZPR-6; reactivity menaurementa tn ZPR-9 eeaem-blies 11 and 12

URANIUM-Doppler effect maaaurementa in ZPR-9’aaaem-blies 12-17 on enriched and depleted

BORON ISOTOPES R-10 — reactivity meaaurementa in largeuranium csrbide faat ZPR-6; react[vlty meaaurementa inZPR-9 aaaembliea 11 snd 12; reactivity worth deiermlnatlonin ZPR-3

VANADIUM-reactivity meesurementa in large uranium car-bide faat ZPR-6; reactivity measurements in ZPR-9 aseem-bllea 11 and 12

LITNIUM-reactivity messuremcnta in large uranium cer-bide faat Z PR-6; reactivity meaauremente tn ZPR-9 aeaem-biics 11 md 12

ZfRCONIUM-resetlvity measurements In iarge uranium car-bide fast ZPR-6; reeciivity measurements, in ZPR-9 aeaem-asscmbliea 11 sod 12

BORCJN CARBIDES—renctivlty meamtremenia In large ura-nium carbide faat ZPR-6; resciivity meaauremenia in ZPR-9a6semtJilca 11 and 12

Nf(~f31U.M—reactivity mcaauremenia in large uranium carbidefattt ZPft-6; reactlvliy meaauromcnta tn ZPR-9 aaaembllea11 and 12

CII[tfJMIUhf — reactivliy meewromcnta in large uranium car-bide ZI~Ii-6; renctlvity worth defermtnatlon in ZPR-3

t URANIUM fSKYlY3PESU-233 — reactivity mcaauromcnis in largeuranium carbide ZPR-6: reactivity measurements in ZPR-9

Laboratory Summary Reports. ..

IRON OXIDES FU203— rescilvlty meaauremenia in large ura-nium carhhio ZPR-6

RHENIUM-reactivity mcaauremcnta in largu uranium carbideZPR-6

Zif{CONIUM I{YI)RILIES—reactivity meaauremcmta in iurgeuranium carbide ZPR-6

TiTANfU.M— rtinctivity measuremonis in isrge urmium csr-blde Z1)R-6

HAFNiUM — rtiactivity meaauremcnts in large uranium carbideZPR-6 .. —.- ..-

EUROPIUM-resctlvitY meseurem’mti in large uranium csr-

.

.

‘1 bide ZPR-6P LUTYMJRJM xSO’iY3PEtf PU-239 — reactivity worth deWrm~a-

‘ - <~Oi-iil ‘2PR-3“ PLUTONIUM iSOTOPES Pu-240-resCtivi~ worth determtna-

tlon in ZPR-3----- . . . . ..

. . . -.

7788 (ANL-7382) RsAcToR DEVELOPMENT PROORAM‘PR~RESS REPORT, SEPTEMBER 1967. {Argonne NstionalLab., 111.). Oct. 31,.1967. Contract W-31 -109:eng-38. 155P.Dep. CFSTi. ,.

. . .

CRITICAL ASSEMIIL1fX+-Doppler $ffcct meamrem~nts inplutonium-fueled ZPR-3; reactor fuel clcmcnts for ZPR -3,[oii-activation meaauremmtta of he~erbg$nclty effects In;rcacti,vity mcmmrcmcnts in acdium-piuionlum core of Z PR-3 pcrturhrd; resonance lntcractlon effects mcanurrmonis. inZPR-9 .,. .

● ☛ ● “

‘ $988 (ANL-7391) l(liAC’t’Oil fJfiVf’:Lol’MENT iUiOGfIAM.Progress Hepori, Oct@ar 1967. (Argorme Natiunul Lab., liL).

Nov. 30.1967. Contract W-31 -109-6W-3(L lnap iJcp.

CFST1.

. . .

~-I;i’iCAL ASSEMBLIES —Doppler co.~-ficle~t and plutoniumsystems atudiea In ZPR-3, summary ofi use of ZPR-!t forFFTF mockup studies; reactivity worfb messurementa in ZPR-3, FTR

.*O

asecmbiic~ i i and 12

84

.

.

19682492s (!NI. -7I27) RttACTOR D?:VELOIJMliNT PROGRAMplllX:I{l;<S lll:l,LJltT, FEl\ll(lAR~ 1968. (Argonne Nntlonnl Lnb.,111.). \lsIr. J(j, l!l(j~m Contract W-31 -109 -eM-31i. 151p. Dep.cFsr[,

● ✎ ✎

CR fTICA L i.<~Ufil BL-tiS-ncuIr(>n spectrum In ZPR -3 Assem-bly 51. crnfrnl, (TI; neutron spectrum In ZPR-6 Assembly 6with nnd W’lth<wtsodium, rcnlrnl, [fz\: S~IUm_VOM cocfflc[ontmrqsoremonte ,In 7,PR-ri As.wmbl,v G .

tJRANIUM ISOTGPES”U-~35”-n&mon ~lgsio~~ates in’EBR-z...

‘E/n:ncutmnflsslon cr0s8 section men fwrementa from 30~0 1500 keV

.99

30118 I !S1,- 74:W) RI: ACTC)R DEVELOPMENT PI{OGRAM.Ptog I’, =- ll(!In,rt, ilarch I?l;q. (Argonne Nntirmnl Lab., Ill.).Apr . :,:, 1:>1:. (’[mtr:!ct W-31 -109 -eng-38. 135P. Dep. CFSTI.

.** . ..CRfTICAL ASSEhfBLIES-rq~ctIvity worth measurement in the

FTR Phsse B mockup in ZPR-3, sddium)reactivity measure-ments tn ZPR-3, effects of,fucl compaction on; reactivitywor~h measurements Ln4000-liter oxide core in ZPR-6; Dopp-ler coefficient mcasuremente In urnnium oxide zoned core ofZPR-9 fast: development and COIMtrUctidn of ZPPR, etatue 88of March 1968 of; reactivity cocff ic ients for, effects of geom-etry on

TANTALUM — reactivity worth of, rneasttreinent in ZPR-3 of,BORON CARBIDES—reactivity worth of, measurement ha

ZPR-3 ofURANRJM-reactivity worth of, measurement to ZPR-3 ofREACTIVITY-Doppler coofficlent of, rneaaurement in uramium

oxtde zoned core of ZPR-9PLUTONIUM fSOTOPES Pu-239— alpha croes section for, ef-

fects on ZPR-3 reactivity of

..*

PLUTONIUM —reactivity worth of, measurement in ZPR-3 Of;separation from ruthenium, usc of trnnepiration technique for;rcmovaf from plutonium hcxsfluorides, effects of presence offluorlne-gm on

.**

3S422 (AiiL-7445) REACTOR ‘DEVELOPMENT PROGRAM.Progress Report, April 1966. (Argonhe Natinnal Lab., 111.).June 12, 1968. contractW-31 -109 -ong-38. 155P: Dep.CFSTI.

Thl@monttilv prngrves report includes informnt’lon on ERR-II,zpff-?, ZPPtf, Lhtf.’l\R, gcnoral rcnctor technology, m-t rcnctornafcty. For detailed In formnt!on, scc the nnnunl rcporh from thefollowing ANL Divislone: Chemical Eng{nccrin~, Mctnllurgy, Ro-scior Englnccring, and Reactor Phyeics. 13 rcfcrcncoe. (J. M.J.)


37401 (ANL-74S7) REACTOR DEVELOPMENT PROGRAM.Progress Report, May 1968, (Argonne National Lab., Ill.).July 2, 1966. Contract W-31 -109 -eng-38. 146P. Dep. CFSTI. -

Thts monthly progress repert includee information on KBWR,LMFBR, ZPR-3, 7,PR-6, ZPR-9, ZPPR, EBR-11, general reactortechnology, and reactor safety Including TREAT operations. Fordetailed information, see the annual reporte from the followingANL Divieione: Cherriical Engineering, Me@urgy, Reactor Engi-neering, and Reactor Phybice. 26 references. (D. C. C.)

42158 (ANL-7460) REACTOR DEVELOPMENT PRCGRAM. .Progre&s Report, June 1968. (ArgoMe Natioml Lab., Ill.).JUIY 29, 1968. Contract W-31 -109 -eng-38. 136p. f)ep.C FST1.

Highllght8 of, project activities are summarized for the monthof Juno 1968.. For detailed summariee, eee the annual repbrtefrom the following ANL divieione: Chemical Engineering, Mctat-lurgy, Reactor Engineering, and Reactor Phyeica. During Junethe EBR-R was opet’nted for 659 MWdt in a run with a full com-plementof fuelcri’experimc@ ’al euhaeaemblies and a referencerun with reflector eubaeeembliea of etainleee steel rather thandcplcfed uranium. Nearly normal production wae resumed In theFuel Cycl. Facility hot line. Experiments continued with the ZPR-3 Assembly 52, the eocond core of Me FTR Phase-B criticalprngram, installation of the ZPPR reactor aesembly and asseci-atcd equipment waa completed, and seal door and containmentstructure testing is in progress. Nuclear safety studiee, includ-ing TREAT operations, and chemical eeparatione activities arediscdseed. (l{.D.R.)

‘50699 (ANL-7487) REACTOR DEVELOPMENT PROORAM.Progrese Report, August 1968. (Argonne National Lab., 111.). ,Sept. 26, 1966. Contract W-31 109-eng-36. l12p. Dep.cFsn.

Righ]lghts of project activities are summarized for the month ofAugust 1966. Fuel ddve.lopment programa for the LMFBR aro de-scribed. Operation of the zPR-3 Assembly 51 and 52 for LMFBRphyske deve!opmente during August 196S are described. Loadingand startup programe nf the ZPPR are proeented. Oporatibne forthe EBR-2 durtng August 1968 are described. Nuclear safety stud-ies, including TREAT operation, and chemical se~ration activi-ties are discueeed. (D. C. C.)

85

1968

32960 (ANL-731O, Pp 31-135) THERMAL REACTORPHYSICS. (Ar@m’e National Lab., U).

CRITICAL ASSEhfBLfES-c admium riatto mcaaurements Inhtgh conversion uniformlattlce,goldmtilrtdlum

GOLD —cttdmium ratios for, measurement in highconverolonuniform lattices nf; cadmium ratios for, determination of ‘

,. neutron temperature and eplthermai index from activation .uWNIUM ISOTOPES U-235—neutron Cross tmCtiOna for,

C4fccts on reactivity of variation of; cadmium ratios for, de-termlqatiort of neutron temperature and eplthermai hdexfrom activation,

...!

$fNDIUM-cndmlum ratios for, measurement tn htghconveratou‘untformlnttlcceofU17ANIUMISOTOPES U-2384 neutron’cross aectlona for, ef-

fects on rcacttvtty of variation ofReactivity-neutron croaa section varlatloh effects on,’

urmlum-235 and uranium-238; temperature effects on AARRcxceas; lnscrtlon accidentp In AARR, maiysla of; translentabt AARR, aummm’v Of renctnr rOq~nne~ tO

.. ..?..-- ~*-..-.EXPERfi?lENTAL BtiILINO WATER ~EACTOR-@sonlng for,

rcnctivlty worth of boric actd; control rods for, reactivity, worth of; temperature coefficient of reactivity for, meamtre-

mcrd of uniform; plutnnlum recycle experiment in. power 0p-rxntlea hffdory of; plutonlum fuel Ioodlng In, mrmfiurcmeni ofcnpturc- to- fisskm rntlo of plutOnlum-Z19 nnd plutonium-241In:.cndm Ium rntlo mcasurcmtmts In, test condttkms for.

NEUTRON CROSS SECTIONS~v~rla~looa tn uranium-235 and ‘uran[urn-238, effects on reactivity of; cfetermioationt of, AARRinternnf thcrmel column effective group

● *9

..3015s INAA-sR-12296) AEC UNGL’ASSIFIE6 PRfXiRAMS. ”Quarterly Technical W%re.sa ReW”rt, October-December 1966.(Atomics International, Canoga Park, Catif.). Oct. 25, 1967.Contract AT(04-3)-701. 151P. Dep. CFSTI. . “

NEUTRON CROSS SECTIONS— evaluation for fast reaotorphy,sics analysis, (E/T)

NEUTRONS— spectra In coolant and atiltctural material of ,sodium-cooled reactora, (E); spectra ttietrthution’ in faat re-actora, analyaie of energy and spatial, (T)

REACTORS, FAST— reactivity vartationa in, Doppler meaaure-ment8 on

REACTORS, LfQUfD METAL COOLED— stability of aodium-cooled, effect of boil tng and two-phase ffow on, (E/T); cooitngayatem of, behavior of fission prcxfucta releaaed in aodtum, -(E); cooiant firea in, energy and fisalon product reiease insodium, (E/T)

REACTOR SAFETY—holant boillng and ‘two-p~ae flow@sodium-cnoled reactors, (E/T); f tpsion product behavior in .,cooling system of sodtum.cooled reactors, [E); coolant fireq

‘ in sodium-cooled reactora; energy and ~iaaior product releaaq,in, (E/T) /

“(REACTIVITY— Doppler coefficient of, mdhodlfor &tertntna- ,$Ion of. (g/T) .-

90.


2739b (AI-AECY12638) ,AEC UNCLASSIFIED PNOWAMS.Quarterly Tectmicai Progrees Report, OciobeeDecemher 1967.(Atumlca International, Canoga Park, Cailf.). Contract A’F(04-3) -701. 209P. DeP. CFST1.

NE uTkON CROSS-SECTfONS —SCORE evaluation systemfor, d.ascription of

THORfUM ISOTOPES Th-232—qeutron cross acttion for,’Me of optical model for t2vaiuatiOn Of . .. $

.99

URANIUM ISOTOPES fJ-238-neutren cross sectiQn for, ume of,ootical model for evacuation of; reactivity worth meamwe-rnenta in faat spectrum reactor

REACTORS, FAST-core for, temperature coefficient of the-rium metai

TNORfUfd —reacUvity worth meaaurementa in fapt spectrum

P~~O~~—DoPPler effect of,’ effects of iaotoplc compoaltion

I&O~CITVITY-wo@ measurements of thorium and uranium-23810 fast spectrum reactor; temperature coefficim,t of, ef- Ifecta of plutonium isotopic content o% worth measurement ofuranit4@?35, effects of mass on

9*9

32740 (ll,\\V-3ti47-7) Pf{YslCS VERII:lCAT1~~ PROGRAM.Flnni Ncfmrt. Unldwin, M. N.; Clark. fl. H.: Rogers,

1~.A~.r ~;ln~~k and WilCoX Co., Lynchburg, Va. Research andDevclnpmcnt Ofv,). Apr. 1968. Contract AT(30-1),-3647.

1123P. Dep. C FST1.

C’RITICAI. ASSEMBLIES-description of B & W Crtttcal Expcr-imcot f.m~oratory uranium ‘bxlde (U02)-fueled water- moderatedmultl - rnd

CtU ITCAL STUDIES— reactivity measurements for aluminum-cind urxnium oxide (UOI) multi-rod water- moderaicd, analy-sis of

REACTOR FUEL ELEMENTS—seuemblies of alum”inum-c]~duranium oxide (U02), criticality of multi- rnd circular

‘ RADIATfON DETECTORS, PROPORTIONAL— calibration ofB k W Criticni Experiment Laboratory multi-rod criticalassembly, deecrlption of

RAD1ATION DETECTOILS, FfSSrON CHAMBER, RADfATIONDETECTORS, IONIZATION CiiAMBER—caitbrntlon ofB & W Criticai Experiment Laboratory multi-rod critlcslassembly, description of

NEUTRONS— radiation menaurement of, effect~ of concrete@hieldtng thickness on B & W Criticat Experiment Laboratorymuitt:rod critical assembly

RE ACTfVITY— measurement of atuminum- clad urantum oxtde(UOJmuitl-rorf water-moderated c?iilcal assembly, ●nalydeof

RADIATION DETECTORS, Activation-measurement ofneutron flux distrlbutien in alumlnurn-clad uranium oxide(UOZ) multi-rod water-mnderated criticai assembly, analysis

‘ of; design of rhodium wire, description of; performance of Irhodium wtr~. deacrlplton ~f: caltbratlon of aluminum-dysprosium wire,.description of; performance of aiuminum-dysproalum wire, description of -

RHODIUM-use for neutron flux measurement, description of, ALUMINUM ALLOYS AND SYSTEMS— At- Dy, use for neutron

flux measurement, descrtptlon of; Al- Cd-In, control rod

1

reactivity worth measurements for, description ofREfACTOR CONTROL ELEMENTS-rnactlvity worth of

aluminum-cadmium- iridium, measurement of (D. C. C.)

.

.

.

.

86

1968 Laboratory Summary Reports. ..,,

bo90 (EURFNR-395) COMPAnlWN OFtiEAStiI{EhIl:NTS !IN SNE.4K-1 AND ZPR 111-41.Bnrleon, L.:iln:hmc, ft.; fYoeJmel,K.; (trod others) (Kernforechungszcntrum, Karlsruhe (WetXGer-msny)). Oct. 1967., 34p. ‘(EUIt_3670~; KIK ti26i~ONF- ‘671043-2), fkp. CFSTI..

Work performed under United States-Kuratom Fast ReactorExchange Progfam.

From Symposium on Fast Reactor Physics umtRelatedSafetyProblems, Karle’ruhe, Germany.

fhtaforcrltical muse mctisuremtmte, prompt neutron decay ‘constant8, flux profiles, und iitmion r&tlos are prt$stmtcxl andcompared for the SNEAK-1 and the ZPR I1f..il reactors, (D.C.CJ

12085 (iNJWL472, PP 3.1-33) THERMAL RKACTORS,t8qMelle-tJorthw60t, Rlchland, Wash. Paclflo Northwec; L*.),

Meimurements to obtain adjolnt weighted exeunt! neutrqn pru -duct ton crons sections were completed for four Iatticeti of PUO, -UOZfuel m grnphlte moderator. ‘ile meaaurementa wure mudcin the llhytiicai Constmta Test Ruactor (PCTI{), and n v:duo ofthe Ini!mtu nte.fiu:n neutron nmitiplicAlon factor (k..) WM ohtuinedfor one I:ittlcti using the tr:tiiitiou:d PCTlt null rtiactlv lly tcchnlque.This ~.duh of k- UAS cwupsrti d with the cor ru~pouding VUIUUob-t:lin.d from m+muremenls for thu n.Imu I;ttticu. An:dynls of theCA F-, Phoenix water refldcted coro with 17 energy groups yieldeda calculated reactivity within 1% of experiment using diffusiontheory snd 3% using transport theory. Pre-experiment calcuiationaon the PRCF-Phoenix ‘core reveaicd that k dropped ae more core-reflector interface detail was added. Final critic.d loading esti-mates were less than 9% low. Placement of flux suppressors forthe MTfl-PhoenLx cere was investigated to avoid having the fu--out flux increases outweigh the close-in flux decreases. A fuil - .cqre bmdted-shim cri-ticsl loading wae achieved in the PRCF-Phoenix fuel experiment, with the shims 65% withdrawn. powerdistribution trvxmurementa in the shimmed core have ahoym theexpt.cmd pnwcr peaking in the fuel foiiowers just below thu bottnmof the coro. Compilation have been Issued of the burnup dataobtained by dcstructiv$ snaiyaia of Ai-1.6 wt % Pu and Al-2.6 yi %Pu fueis which ucre irradiated in PRTR.’ Analysis of the burnupdata frnm the Aiuminum - Plutonium fuuls irradiated in PRTRwas completed. The isntopic concentration data were proccseedusing multivarisble regression anaiyeia to obtain a unique set ofcrom eection ratioa. An empirical formula was derived for uaein fitting critical maes data from cylindrical arraye of rode,meckrated with H20. The formula provides a method nf accurateinterpolation to obtain the fuel-tb-mnderator ratio for m,inimumcritical mass. Relative rnd power measurements were made in’PRTR to determine the pewer match between fuci ro@ in eiemc~iiin the Batch Core and fuel reds in several possible test configura-tions in the Fuel Element Rupture Test Factlity (F ERTF). Therelative red powers wer$ determined by gamma ecanning. Thereactivity changes assnctsted with leas of coolant from the PRCF ‘were also meaeured for sevcrai fuel compoaitiona and test con-figurations. A theory-experiment correlation study of ratios ofeffective crose aectione wak performed. A result of the study isthat the c:iicuiated ratioa agree beet with the cxperimcn!:ii ratioeudng the Leonard norrnniization for the 21$PUmd 24tPu tilermui

. croad acctiona. Calcdationa nf the photnneutron production inD20 ,modci ~tcd reactor syetema fueled with lY-rnd clusters ofAl - Pu, U02- PuOZ, and UC were made, A cnlcuiutiomii study wasmade comparing vqiues of the Dancoff correction obttiincd via ‘various methods. TIMIco~respondhg effect of resonance intcgreiaatwf reactivity were also determined. Calculations were made ofpower peaking factors in H20 moderated loadlngs of U02-2 wt %PU02 fuel. The calculated vaiues agree with measured vaiuea towithin *5’i,. Calcdations were performed to help predict criticalmasaes and various iattice parameters f~r HZO moderated iatticeftcontaining U02 -4 wt % PuOZ fuei rods. The study wae made assum-ing two types of fuel differing in ’40Pu content. (auth)

12086 ““ fSNWL-t72, Pp 4.1-43) FAST REACTORS. (Bnt-telle-Northweato Richiand, Wash. Pacific Northweet Lab.),

A survey was perfnrmed to lnventigtde tho effect’ of BeO on FTRneut ronica. I@ms con~idercd included the aodiu m cocff iclcnt,Dnppler cnefficlent, critical mass, and flux spectrum dcpcndonceon BeO volume fractions.’ A detatlod analysis of FTf7 control rodconfigurations wae carried out. A variety of represent nt ive rodputter no were examined and their reactivity worth determined-The effectn of fuel faiiure and fuei relocation (eiumping) III the ,FTR are bebrg re-examined. A aeriee of kinetics cnicuiationswere performed for a range of reactivity ramps and shutdowncoefficients. ‘i%e poaeibie qtilfaation of fuel-rod piuge to minimizethe effecte of fuel slumping waa ciao considered. To check csicula-tlonai technique used in FTR deeign, anal ysfs of the and ium voidexperiment pcrfnrmed on the SEFO17 mockup in ZRP-1~1 wasundertaken. A fairly dctailad ansiyaie of the Deppier coefficientmeasurements in the same paecmbiy Is aieo being ctirricd out.f.rworporatinn of cryataliine binding effecte in the wmiyeis cauaedthe ~ppier coefficient tn diverge from tbe l/T dependence in”qualitative agreement with the experimental results. The two.dlmensiomd poriurbations cede, 2-D PERT, 1P hot nporutionni,‘fhia cede wiil be used for driver fuci dnd tcrnt mwragemunt aiudies.~e Phtise-A critirmi exiwrimonta in ZPi{-IIi were” completed, .und wralysia of the experimcnte was started. The aitcnu.ttiuncharticteri~tic~ of a number of aitcrn:de ,Bliiclti :’rr:m~uto,:n! Bwere’compared Jnufytictiiiy to providu a b:tmimfur the couculjtuuid,:~iKn of iho k’”1’ii, }:stimotoe of g:tmma intcnrnlty itt rnclectdlocations within iwo diffuront closad ioop celi concepts www uleomade. (auth)

87

196814251 (flN\i L-50\) REACTOR PHYSICS DEPARTMENT ~TECIINICAL ACTIV1T1EX5. Quarterly Repnrt, Afrrll-June 1967.(Battclle-Nort@ est. Rlchlnnrf, Wash. Pnclfic Northwest Lab.).Jan. 1968. Contract AT(4S-1)-1830. 84P. Dep. CFSTI.

NE(’TRON CROSS SECTIONS —annlysls of, use of optical modelfor theoretical

COMP(U ER PROGRAMS-description of fast reactor FCC-IV. ,RF ACTOR F(’EL EL Ehl ENIV—rcacllvity worth of I?RTR, mr=a-

surcmcnt OL power distributions {n Phocnlx, measurement InPRCF OR neutron multiplication factors for Phoenix, corn-pnriwwi of ●xperimental and calculated valuca for; Dopplercocf[irkmts [or FTR, effects on fuel temperature of varlatlonod .,

PL(’TX)NILIM RHCYCLE TEST REACTOR —neutron fluxes in, orntlw of axial peak-to-avcrngc; fuel element recycle testfw-ility for, mraaurcme,nt of fuel clcmcnt rcac!lvity ~ortha in

BCrfKJN—reactivity worth of, PRTR hatch coro measurementof

REAC’IWRS— Inttlcc frarnmctem for uranium dioxide 19-clustcr, mralysis using R f3V Monte Carlo code for; fuel latttcesfor, tcmpcraturc cocfflclcnt calculntlons for uranium-233 oxide(UOI) - thorium-232 oxldc

PLtTTONILlhI RECYCLE CNITICAL FACIIJTY-reactivityworth measurements of Phoenix core In

HIGN-TE31PERATURE LATTICE TEST REACTOR —DoppIer .’coefficient measurcmenta for, procedures for

FAST TEST REACTOR —phyaica characteristic of, analysiaof split-cone; control rods for, reactivity worth of safety.accident conditions in, fuel pln center-llno temperatures un-der; control reds for, calculations of re+ctlvlty worthn ohcomponents for, heat generation rates and neutron damagerates In

REAC~R SAFETY— FTR fuel pl~ centerline tenlperature un-der accident cooditionn ‘

CRITICAL ASSEMBLfES-Doppler cocfficienta for ZPR-3, 4comparison of measured and calculated valuea for; neutron ,fission ratea in ZPR-3, uranium-238 and plutordum-239;neutron spectral measurements In ZPR-3 and ZPR-6,

t~ANIUhI fSOTUPES U-238— neutron fieaion rates in ZPR-3PLUTONIUM ISOTOPES Pu-239 — neutron fission ratea in

ZPR-3REACTOR CONTROL ELEhlENTS-reactivity wort calcula-

tions for FTR “ !URANYf, NITRATE —critical uranfum-23S enrichment for eo,-

Iutlons of, determination cf uraniumREACTIVITY- wnrth of uranyl nitrate aa ,function of Urani m-

235 enrichment dcdermlnation of maximum e%ce86 rPHYSICAL CONSTANTS TEST REACTOR &reactivity worth

measurements In, determination nf criticai uranium-23S en-richment for uranyl nitrate, using’

NEUTRONS— monochromatization of, use of multiple Bragg ‘. reflection for hfgh-meolution

Cil MGEf) PARTICLES— rc~atlvistic motlnn of, description ofrfwnfrutvr prrrgram for calculntlng and plottlng ci@t-dimcntrlrrnal phs6e-npacc clrctrom.agrwtic plane wave-drivenIhf 1,.S.)

1

,.

Laboratory Summary Reports. ..20779 (BNWti24,pp3.1-159)REAC’rORPHYSICS.(I\attelle-Northwcat, Rlchland, Wa~h. Psclflc Northwcat Lab.).

Expcrimmrts wcm conducted In the Critical Approach Fncl!ityand tho Plutrmlum Recycle Critical Facillty to lnvm!tlgatc the ‘de-tallcd physics properties of plutonhrm-fueled rcnctor systcmmMcnsurcments have bcmr mafin usbrg U02-2 wt T PuOI rodn InH20 modorator. Experiment wcro conducted nt I:lttlce epaclngccovoring the rrmgo of mnderatfrr to po~ - U~ volump ration of0.61 tn 9.7 and tho plutmtlum contained either 8. ifi or 24’%‘t~pu.*ho rcsulte includnd critical masses, tmckliirgn. fl,,x and proverdistributions, reactivity coofftclente, klncllc pnrsmvtcrs, andcontrol rod wortha. Tho PCTII Ie bclng urml for cvaluntlng theof fcct on rcnctlvlty of finite Pu02 pnrtlclca in U()* mvf for obtalo-brg additlonnl.datu nn wntcr lattices not otiainalde from other fa-ciiitlce which arc rcqulrcd for further cvalustlon of analysle meth-ods. Tbc initial rcsuits of the Pu02 partlclo eize expcrlmcntsindicnto that the reactivity decreaece ss, the eizc ie fncreasedfrom 100 P to 350 v f~r the fuel compoeitlon used (2.0 wt % Pu~,8.05 wt % 140Pu). The design of the ffret experiment in the Watertank is completo end will contain PuO1- @ fuel on a 1.0 tn. lat-tice pitch. A large scnle burnup experiment hae been lnltlatedin the D20-moderated Plutonium Recycle Test Reactor uabrg 19-rod clusters of U~-2 wt % Pu02 rods: The firet phase of theexperiment has been completed and consisted of an extensiveset of tests at zero power during tbe ‘lnitldf loading of the core.A series of pewer teeta dcalgned primarily to verify predicted ,operational chsractcrietics of the reactor were ‘cooductecf w~enthe ioadihg wae completed. An irradiation experiment wse con- ,,ductcd In the Experimental BoUing Water Reactor at ArgonneNational Laboratory. Thie experiment ie part of the joint ANL-PNL “program to demonstrate the utilt?!at!on of plutohl~ in a bdltngH20 power reactor and to obtain ueeful phyeice information on thebehavior of a plutonium fuel is euch a reactor system. At threestegee of burnup a eerlee of rods were removed frnm the plutoniumzone for nondestructive and destructive snsiysis. The seriee ofrode contained A1-Pu, natursf U02, and U~-Pu02 fuels. In addi-tion, the fuels which contained plutonium differed in their ‘topuconcentration. Some of the roda sre eelected fmm positions in thecore eo that the spattai dietributlon of burnup can be obtaioed fromthe nondestructive end destructive analysis. Fuel rods removedfrom selected locations in the EBWR end from psst and preeent ex-pe~menta in the PRTR are brrth nondestructively and destructivelyenniyzod to .obtsin flsston end fuel concentration sod isotopic com-position. From these dafs effective crose section ratios arederived for asf in evaluating hutmup snelyede methcds. New tecb-ntques for this purpose tiefng multi-parameter, non-linear regres-sion methede have been developed and applied to data from fouraeta of irradiated A1-Pu samples. The PNL Gamma Scanner hasbeen lrnproved and continues to be used for the nondeetructlveanrdyeie. Information” on the physics characteristics of pressurizedw atcr power reactor ayeteme which were obtained during tbe Sax-ton plutonium program ia compared to rcaults obtsined with zero,one, and two-dimensioned diffusion Urcory methode. The ca’icluetonreached is that p one-dimcnelonni cyllndrfcaf model of the reactorseems adequnte from the standpoint of reactivity ceiculstions forelngle zone iattlccs. Analytical eurvey studies have been performedto providn information on the physicg chsrscteristtce for verlousreactor aysteme of fntereat. It ia shown thst the U~-4 wt %Pu~- H20 cores whtch were studied would be undermoderated andthat the chnractcrtstic parameters edch as q, f, and p play en irrt- “portsnt role tn the phyelca behavibr of thes6 cores. A survey atwrfywas conducted to determine the npprdxhnste mngnltude of variousreactivity cocffictente for UQ-PuOt fueled llgbt water reactorr.Cnlculntlone wcro sleo. pefformed to determine the reactor charac-tcrlmtlcfr of thorium Ionrfings In II@ modcrnt(,r. The fensiblllty Otthe tlwrlum londinK [n the PRTff WRS dctrrmlned clthcr as s batchcor~ or n~ n driver rcglun for n U(} - Pm} core. The ph}elcschnrnctr--rlnth-s of mctnttlr furl nml of rernmk- fucln were investl- .gntcrf rdonx w ith Ilw cnrlatkm in md SIZO fn thorium enrichment.Slow neutron inelaetid w attcring cross wcttonn hsvc hecn reportedfor RIO ●nd Lll(l. The double difforcntlal cross section and corre-epomfbuf F.grlstnff scstterint law have been obtstqd from rnemnm- “mmtts for rrrom temperature H*Osnd ~0 ●nd for H@ of five de-arees below its fmeztnc wtnt usttw the Dattnlle Rotstfng Crystsf

“

-.

1968 Laboratory Summary Reports. ..

Uma-of-fllght t@otromeutr. fo Adltltm, retiulto of measure-’munts [W 111()●I s5°C ustng the Battello TTlple-kltt Spectrorn-ater havo bmm rrfamled. An extenulvo ovaluotion of the RUU MonteCarlo Code hus boa cuml)lu!cd. RVISUIIIIof this tivnluutlon bu!l-ca:o ttutl the R1!11hlunte c’arlu cod.! lb truo of ~rornrnprokrnm er-rurb aItd ,An IIC ubA”reli8My fur rru,. mr phytilcu ~.nlculnlluns.Ku,!* liif~u .d the Lcgemlru uwnlcti!s of modurotor nc’ullcrlng urotwmw.ll,, nbI.J of partlculnr init. h~rlum.mhi Iho prULitL. tkMI (If Iho thermal❑ eutron spectrum of plutonium fueled renctors. Based un theEgclstsff-*hufiuld formsllrnm, two methods for calculutlng scatter-ing moments for moderators have been developed md programmedon the computer. A modol for water IS bctng evaluated using av@l-able experimental data. Sweral computer codes have been adapted,modified, or improved for use in tbe physics programs. The NBUMonte Carlo code has been thoroughly tested and appears to beworking satisfactorily. The ZODIAC-2 burnup codo was modifiedand enisrged to fncreaae Its burnup oapabllitlcs. The HRG (Nan-ford Revised GAA1)code spectrum model uaecj in rwaonance Inte- ‘grsi calculations was improved. Severel special purpose codoehave been developed. Aasistam!e w,aa provldcxf to BrookhavenNational Laboratory tn preparing nuclear data for the ENDF/B.Data were furnished for the tcn isotopes which BnttelIe ncccptedresponsibility to evaluate aa a member of tho Croetr Section Evalu-ation Working Group. Adaption of the ENDF/B system to the locsiUNIVAC 1108 is br progress. Theoretical atudfea have beett di-rectedtowsrd developing a mathematical physics morfcl wtrich ac-curately predicts thp observed physics behavfor of power r=ctoi’systems. A measure of the vatidity of the mathematical model ieobtained by comparing measured and calculated integral parsm-etera such as reactnr multiplication end effective croae sectiorta. ‘Comparlsona bsve been performed for numerous plutonium and/oruranium fueled If20 lattices. Comparisons of flux and power den-sities, reactivity coefficients, kinetic psrqrneters, and affective ‘cross section ratios, have also been made. The resulte of thecompsrison8 show that in many cases the oelculationai techniquesneed to be refined. (euthl

32743 (f3NWL-739) PLUTONIUht, UTILIZATION PRoORAM.TecbtttcefActlvttiocQuarterly(leport,December1997-February1968. (Battelle-Northwest, Ricbland, Wash. Pacific NorthweetLab.). Apr. 1966. Contract AT(45-1)-1830. 84p. Dep.CFST1.

,- --,, ● ☛☛✍ �✎✎ ✎� �✎

PLUTONIUM OXIDES Pu~--l%02-U02, radiation effecta on,amdysia of neutron; Pu~– U~, fuel loading for PRC F re-actor of, phygi:s measurements for critical, [E/T)

● ☛✎

CRITICALITY STUDIES— mwtsurcmerrt of plutonium ox!de(PUO,} –uranium oxide ([f~), effects of plutonium rmrlchmenton. (k/Tl

421b4 (BNWL-775) REACTOR PHYSfCS DEPARTMENTTECNNICAL ACTIVIT1tMl QUARTERLY REPORT, JANUARY-MARCR 1966. fBsttelle-NorUtwent, Rlchland, Wash. Paciftc

Northw’cst IA?.). July 1968. Contrnct AT(45-1]-1830, ll14p.Dep. C FSTI.

. . .

CRfTfCAL ASS KhIitLIFX —kinetics for plutorilum oxidd (1%102)-urnrrium oxide (U02)-fucletf NPTF, comparison with FTR of

. . .

PLtiTONfUM NITRATES Pu(NOt)i —criticality of .slab-8haped;analysis of

CRITI~ALITY STUDIES —rqeart~remcnt of nlnb-ahnpcd pluto-nium nitrnto (PU(NOS)4), dcscriptimr of; measurtimcmt ofrectangular-shnpcd polystyrene -plut6nlum oxide (~OZ)lntticcs, doncrlptton of

PLUTONfUM OXIDES ,W02 —polystyrene -1%02,’ critlcfllity ofrectmgula r-shapnd Intticcs of, nnalysis of (D. C. C.)

2091 b (ANI.-Trnne-556) EXPf2R1h1F,NTA1. STUDY OFNF[l TRON CIIAflACTERfSTICS IN FAST MULTIPLYING MEDIA,USING TR~ Tilk RMA1,- FAST CfUTICAL ASSE NfflLY ,“ ERMINE.”k30uchard, J.; hlougniot, J. C.; Vidrd, R. Translated for ArgonneNational Lab., 111., from Paper Presented at Conference on FastRcnctor Phyetcs and Related Safety Problems, Karlsruhe, Ger-manv, Ott. 30- Nov. 3, 1967. 22p. (t20NF-671043-16). Dep.CFSTI. JCL $2.60 fs, $I.1O mf.

The fnet-thermal ERMfNE aeeembly ‘fn the MTNERVE reactor iede ecrlbed. Reactivity and flux measurements and meaeure mr?nttechniques are deqeribcd. Doppler effect and neutron importancemeaeuremente are diacuesed. Spectral fndex values are tabulated;results of reactivity measurements are Iiated. Data are showngraphically. ( hf. L. S.) ..

. .REACTIVITY— mcasuremcn~of PRf, F uranium oxide (U02)-

fuelc[i core excess, analysls of; measurement of effects ofboron crmccnlratlm tn watrr {m TTR, analysis ef, {E/Tl

PLUTONIUM RECYCLE CRITICAL FACILITY- c:rc loading,fnr, reactivity meaaurcmcnta fdr ursrtium oxide (U02) and

, plutonlum oxide (PuoJ– uranium ordde (U02),URANIUM OXIDES UQ— fuel loading for PRCF reactor of,

ph~slcs measurements for crltlcaf, (E/T) . ,’. ‘

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1968

49817 (EURAEC-2036) U5E bF PLU’iWNiWM AS NUCLEAR~f6~TOR FUEL. Quarterly Report No. 17, January l-March 31, ~

(Centre d’Etude de l’Energie Nucleaire, Brussels (Bel- ,gtum;). Apr. 196S. Contract 001-64 -1-TRUB. 70P. (EUR-3986; BN-6804-01). Dep. C FSTI.

Work Performed Under Untted States-Euratom Joint Researchand Development Program.

Fabrlcatfon of the 260 homogeneous fuel rods containing 2% 2?SVand 2.7% ~~RI ia completed. Fabrication has started en the maktngof 2S0 hcteregcncoua type roda confalnlng 2% 2S1Uand 2.7% 23SPU.A part of thcso rods will be fabricated in the self-contained unit cmthe pneumatic vibrator. Checking of the chlorine content of theplutontfcroua ro’ds has continued aatlsfactoriiy. Two checking pro-ccdurea d tho density mcasuremcnta with mercury and the deter-rolnation of the humidity content d solid samples have been catab-Iiahcd. A new series of eight trip burnouta has been carried out tathe burnout teoting. The results on fuel aaecaament d the dimen-sional meaeuremcnta and the tapping teats are,gtven for the atxrods irradiated In hydraulic crmveyor (IiR-1 rune 5 and 6). Theswelling of tire rods reached several per cent and there ia a dtf-ferenco bctwccn the homegcncoua and hctcrogcnecme rods in corn-poslt[on and volume d gaa collected. Tw9 irradiation tests etthree Zircaloy 2 clad fuel rrxfa havo been effected in hydrauiiccrmveyor at a power rate in the region of 770 W/cm (HR-1 r’yna 9●nd 10). Foilowing the 9 and 10 111{-1 runs, lhrce sets d threeatnlrdcaa atcol clad fuel rods we] c irradiated up, to a power of1290 W/cm. The dimcneimml mcmurcmcnts cffcctcd before and .after Irrndlation showed that thr hrnnngcnocue rods had awollcn by .atmut 1 to 2%, while the hctor~,cncoue rode hnd rotaincd their lni-thl dimcneirxrs. The maximum power ntL~lncd In CMR-4 1s 800W/cm. The bum-up raUoa are 22500 MWd/t in the homogwmcuarod nnd 18500 MWd/t In the hcterogcnccxm red. The PANTIIERcode haa been improved by prucccdlng with the treatment of thehf,tcr~cnrity in the fast field, the Immdcning of tho rcaarancc ofWI}, at i OS CV ~111, Ih(. tfim~ratllrc, and mmilflcalfmm tn the fact ‘

liimiry o; some I-otnprs. The rectangular configumtlnn with a1.3WI cm aqnarc pitch has hccn atudlcrl wllk ,4/0 fud. The criticaimuss has been determined, Iogrthrr with tfw nxiai and rarlinl buck-lin~s. Tho reactlvc effects and the power diatrlbutirms have beenmewmrcd in the presence d a ❑umber of pcrlurhatinns (waterfiims, ●luminum plate, RbKr)rbent rods). AnalyokI of the data fromtho nub-crlttcai VI?NUS- Vuicain tests haa ccmtinued. A auppic-mentary prqmarn of sub-critical tests cm 4/0 fqel with an N~pitch hns Iwrn outltncd. The study of the power distribution duringthe 5Ut CYCIChas been undertaken in tho caao where tho 7th coreiaycr contains a Uq- PU02 area with 3.6 wt % cf pu~. (J. C. W.)

39875 (Bf4L-5o082, IT 1-18) I% AcToR pHYsICS DIVISION.,Chernick, J,; Koute, H. (Brookhavc’n National Lab., Upton,N. Y.).

Developments are raperhd for etudiea on: reactor rafety; Natemperature coefficient di etribution in plenum reactorB; fast re - ,actor criticats: fast neutron traneport; reactor dynamica; neutronthermaft zation; iteration metheda; reactor kfnetice o fluid dynam!ca;reactor physics RAMMER CODE; anaiyai.a of BNL ‘sCU-graphitecriticaf expertmenta; andtysie Ot Brookhaven ‘~af.l-ThOz latticqa: “npectrum-shift lattice experiments: smatl reflected assemblies;urmlum-graphite critical aaaembltes; californium experiment;txu~ _~~ _~o e.xponentid experimonte; aaiaotro~ of Oeulronmigration; phyaica of faat Na-cooled reactors; and eupport workfor experimcnta. (D. C. C.) ‘


50%47 ‘“’”” “FISICA DEL tiEAT~RE. cotiiIEGNo INDETToDAL1, A, SOCiE’rA LOM13ARDA DI FLSICA, MILANO-PAVIA,DICEM13RE 1963. (Reactor Physics. Meettng of the LombardaPhyaice Society. Milan-Pavia. IfalY. December 19631. ~on-greeet, Conve~”i, e Slmpoai scien~lflcl. 9. Rome,” ConetglloNnzionate delle Ricerche, 1966. 857p. (In English and Itallan)o(CON F-469).

fncludcd are 66 papers on thcorcticat and experimental methodsfor the anaiysis of nuclear reactor, phyaica. Indlvlduaf abatractawere prepared for 61 papera. Abstracts of the remalnlng S papershave appeared in previous iasuea of NSA. The abatract number ofone paper is NSA 19: 12796 and the other 4 papera may be locatedunder CONF-469 in the report number indexes. (H. D. R.)

Fo; abstracts of individual papers see: 4888S, 49074, 49101,49102, 49776, 50.?35, .50339, 50S10-50516, 50604 -5rXCW. 50752-50754, 50760-50765.50813-50819, 50622, 50825, 50826, 5063#–5W33, 50846, 50848-50854, 50861-50866, and 50868-50671.

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la-4225-ms, ----- .-. ,*. —-. c3 ,-...(autb) 1 m. 1967 .,-. critical experiments: reasonably...

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